Low-energy neutrons in FLUKA¶

Low-energy neutron transport is activated by option LOW-NEUT, but it is requested by defaults with most of the options available with the DEFAULTS command (CALORIMEtry, EET/TRANsmut, HADROTHErapy, ICARUS, NEUTRONS, NEW-DEFAults, PRECISIOn, SHIELDINg), see. The only exception is the DEFAULTS option EM-CASCAde. However, command LOW-NEUT may be still necessary in order to define the cross section library used, or to issue special requests. The FLUKA traditional way for neutron transport below 20 MeV is a multi-group approachMultigroup neutron transport, which is fast, compact, and very reliable. It is particularly suited for shielding problems. This approach is inherently inclusive and it does not preserve correlations. Energy and momentum are conserved on average.

However for some problems where the fine structure of the cross sections (resonances) must be explicitly treated, and/or correlations among products are important, the multigroup approach cannot be used. Starting with FLUKA2021.2 an alternative approach based on fully correlated continuous (pointwise) cross sections is availableFull pointwise transport.

Multigroup neutron transport¶

Low-energy neutron transport is activated by option LOW–NEUT

Transport of neutrons with energies lower than a certain energy is performed in FLUKA by a multigroup algorithm. The energy boundary below which multigroup transport takes over depends in principle on the cross section library used. This energy is 20 MeV for the 260-groups library which is distributed with the code. In FLUKA, there are two neutron energy thresholds, for high- and low-energy neutrons. The high-energy threshold marks the boundary between continuous and discontinuous transport and is computed automatically from PART-THR and/or LOW-BIAS. PART-THR no longer controls the transition between model and group treatments: it sets the actual lower transport threshold, whether it falls in the group regime or not.

The multi-group technique, widely used in low-energy neutron transport programs, consists in dividing the energy range of interest in a given number of intervals (“energy groups”). Elastic and inelastic reactions are simulated not as exclusive processes, but by group-to-group transfer probabilities forming the so-called downscattering matrix.

The scattering transfer probability between different groups is represented by a Legendre polynomial expansion truncated at the (N\(+1)^{th}\) term, as shown in the equation:

\[\sigma_s(g\rightarrow g^\prime,\mu)~=~\sum_{i=0}^N\,\frac{2i+1}{4\pi} {P}_i(\mu)\sigma_s^i(g\rightarrow g^\prime)\]

where \(\mu~=~\overline{\Omega}\cdot\overline{\Omega}\,^\prime\) is the scattering angle and N is the chosen Legendre order of anisotropy.

The particular implementation used in FLUKA has been derived from that of the MORSE program [Emm75] (although the relevant part of the code has been completely rewritten). In the FLUKA neutron cross section library, the energy range up to 20 MeV is divided into 260 energy groups of approximately equal logarithmic width (31 of which are thermal).

The angular probabilities for inelastic scattering are obtained by a discretisation of a P5 Legendre polynomial expansion of the actual scattering distribution which preserves its first 6 moments. The generalised Gaussian quadrature scheme to generate the discrete distribution is rather complicated: details can be found in the MORSE manual [Emm75]. The result, in the case of a P5 expansion, is a set of 6 equations giving 3 discrete polar angles (actually angle cosines) and 3 corresponding cumulative probabilities.

In the library, the first cross section table for an isotope (isotropic term P\(_0\)) contains the transfer probabilities from each group \(g\) to any group \(g^\prime\): \(\sum_{g\rightarrow g^\prime}/\sum_g\), where \(\sum_g\) is the sum over all the \(g^\prime\) (including the “in-scattering” term \(g^\prime\,=\,g\)). The next cross section table provides the P\(_1\) term for the same isotope, the next the P\(_2\) multigroup cross sections, etc.

Possible artefacts¶

The multigroup scheme adopted in FLUKA is reliable and much faster than any possible approach using continuous cross sections. However, it is important to remember that there are two rare situations where the group approximation could give bad results.

One of such situations may occur when each neutron is likely to scatter only once (e.g. in a very thin foil) before being scored: an artefact then is possible, due to the discrete angular distribution. In practice the problem vanishes entirely, however, as soon as there is the possibility of two or more scatterings: it must be kept in mind, in fact, that after a collision only the polar angle is sampled from a discrete distribution, while the azimuthal angle is chosen randomly from a uniform distribution. In addition, the 3 discrete angles are different for each \(g\rightarrow g^\prime\) combination and for each element or isotope. Thus, any memory of the initial direction is very quickly lost after just a few collisions.

The second possible artefact is not connected with the angular but with the energy structure of the cross sections used. The group structure is necessarily coarse with respect to the resonance structure in many materials. A resonance in a material present in a dilute mixture or as a small piece cannot affect much a smooth neutron flux (case of so-called “infinite dilution”) but if an isotope is very pure and is present in large amounts, it can act as a “neutron sink”, causing sharp dips in the neutron spectrum corresponding to each resonance. This effect, which results in a lower reaction rate \(\sigma\phi\), is called self-shielding and is necessarily lost in the process of cross section averaging over the width of each energy group, unless a special correction is made. Such corrected cross section sets with different degrees of self-shielding have been included in the FLUKA libraries for a few important elements (Al, Fe, Cu, Au, Pb, Bi): but it is the responsibility of the user to select the set with the degree of self-shielding most suitable in each different case. It is worth stressing that non-self-shielded materials are perfectly adequate in most practical cases, because the presence of even small amounts of impurities is generally sufficient to smooth out the effect. On the other hand, in regions of non-resolved resonances the multigroup approach is known to give very good results anyway.

Partial pointwise transport with groupwise cross sections¶

For a few isotopes only, neutron transport can be done also using continuous (pointwise) cross sections. For \(^1\)H, \(^2\)H, \(^3\)He, \(^4\)He, and \(^{12}\)C, it is applied as a user option (above 3.05 eV in \(^1\)H, \(^2\)H, if requested bound, at all energies for \(^3\)He, \(^4\)He, and \(^{12}\)C. For the reactions \(^{10}\)B(n,\(\alpha)^7\)Li in \(^{10}\)B, and \(^{14}\)N(n,p)\(^{14}\)C the alpha and proton respectively are explicitly generated. \(^6\)Li pointwise treatment which was implemented in the past for the lowest part of the energy range is now no longer available, since a much more complete treatment can be requested using the full pointwise treatment (see Full pointwise transport).

Secondary particle production¶

Gamma generation¶

In general, gamma generation by low-energy neutrons (but not gamma transport) is treated in the frame of a multigroup scheme too. A downscattering matrix provides the probability, for a neutron in a given energy group, to generate a photon in each of a number of gamma energy groups (42 in the FLUKA library), covering the range from 1 keV to 50 MeV.

With the exception of a few important gamma lines, such as the 2.2 MeV transition of Deuterium and the 478 keV photon from \(^{10}\)B(n,\(\alpha\)) reaction, the actual energy of the generated photon is sampled randomly in the energy interval corresponding to its gamma group. Note that the gamma generation matrix does not include only capture gammas, but also gammas produced in other inelastic reactions such as (n,n\(^\prime\)).

For a few elements (Cd, Xe, Ar), for which evaluated gamma production cross sections could not be found, a different algorithm, based on published energy level data, has been provided to generate explicitly the full cascade of monoenergetic gammas [Fas01b].

In all cases, the generated gammas are transported in the same way as all other photons in FLUKA, using continuous cross sections and an explicit and detailed description of all their interactions with matter, allowing for the generation of electrons, positrons, and even secondary particles from photonuclear reactions.

Secondary neutrons¶

In the multigroup transport scheme, the production of secondary neutrons via (n,xn) reactions is taken into account implicitly by the so-called non-absorption probability, a group-dependent factor by which the weight of a neutron is multiplied after exiting a collision. If the only possible reactions are capture and scattering, the non-absorption probability is < 1, but at energies above the threshold for (n,2n) reaction it can take values larger than 1.

Fission neutrons, however, are treated separately and created explicitly using a group-dependent fission probability. They are assumed to be emitted isotropically and their energy is sampled from the fission spectrum appropriate for the relevant isotope and neutron energy. The fission neutron multiplicity is obtained separately from data extracted from European, American and Japanese databases.

Generation of charged particles¶

Recoil protons and protons from \(^{14}\)N(n,p) reaction are produced and transported explicitly, taking into account the detailed kinematics of elastic scattering, continuous energy loss with energy straggling, delta ray production, multiple and single scattering.

The same applies to charged fragments from neutron capture in \(^{10}\)B, and from all reactions on \(^2\)H, \(^3\)He, \(^4\)He, and \(^{12}\)C, if pointwise transport has been requested by the user. All other charged secondaries, including fission fragments (see Residual nuclei), are not transported but their energy is deposited at the point of interaction (kerma approximation).

Residual nuclei¶

For many materials, but not for all, group-dependent information on the residual nuclei produced by low-energy neutron interactions is available in the FLUKA libraries. This information can be used to score residual nuclei, but it is important that the user check its availability before requesting scoring.

Fission fragments are sampled separately, using evaluated data extracted from European, American and Japanese databases.

The FLUKA neutron cross section library¶

As explained in Installation, an unformatted cross section data set, or library, is needed for low-energy neutron transport. For a description of the algorithms used for tracking low-energy neutrons, see Multigroup neutron transport. Other useful information can be found in the Notes to options LOW–NEUT, LOW–MAT and LOW–BIAS.

The Legendre expansion used in FLUKA is P5, i.e. at each collision the polar scattering angle is sampled from three discrete values, such that the first 6 moments of the angular distribution are preserved (the azimuthal angle is sampled instead from a uniform distribution between 0 and 2\(\pi\)). The energy group structure depends on the cross section set used. Here below the group structure of the currently available sets is reported, and a list of the materials they contain.

The default FLUKA neutron cross section library (originally prepared by G. Panini of ENEA [Cuc91]) contains more than 250 different materials (natural elements or single nuclides), selected for their interest in physics, dosimetry and accelerator engineering. This library has a larger number of groups and a better resolution in the thermal energy range in respect to the original one.

The preparation of the library involves the use of a specialised code [NJOY] and several ad-hoc programs written to adjust the output to the particular structure of these libraries. The library is continuously enriched and updated on the basis of the most recent evaluations (ENDF/B, JEF, JENDL etc.). The library format is similar to that known as Anisn[Eng67] (or FIDO) format, but it has been modified to include kerma factor data, residual nuclei and partial exclusive cross sections when available. The latter are not used directly by FLUKA, but can be folded over calculated spectra to get reaction rates and induced activities.

More materials can be made available on request, if good evaluations are available. Some cross sections are available in the library at two or three different temperatures mainly in view of simulations of calorimeters containing cryogenic scintillators. Doppler broadening is taken into account.

Note that the energy groups are numbered are numbered in order of decreasing energy (group 1 corresponds to the highest energy).

The default FLUKA neutron cross section library has 260 neutron groups and 42 gamma groups. Gamma energy groups are used only for (n,gamma) production, since transport of photons in FLUKA is continuous in energy and angle and is performed through the Emf module).

Hydrogen cross sections, which have a particular importance in neutron slowing-down, are available also for different types of molecular binding (free, H\(_2\)O, CH\(_2\)).

At present, the FLUKA libraries contain only single isotopes or elements of natural isotopic composition, although the possibility exists to include in future also pre-mixed materials.

Neutron energy deposition in most materials is calculated by means of kerma factors (including contributions from low-energy fission). However, recoil protons and protons from N(n,p) reaction are produced and transported explicitly (see Generation of charged particles above).

Each material is identified by an alphanumeric name (a string not longer than 8 characters, all in upper case), and by three integer identifiers. Correspondence with FLUKA materials (standard or user-defined) is based on any combination of name and zero or more identifiers. In case of ambiguity, the first material in the list fulfilling the combination is selected. (See command LOW–MAT, for more details).

The convention generally used (but there may be exceptions) for the three identifiers is:

Atomic number
Mass number, or natural isotopic composition if negative (exceptions are possible in order to distinguish between data from different sources referring to the same nuclide)
Neutron temperature in degrees Kelvin

260 neutron, 42 gamma group library¶

Neutron and gamma energy groups¶

The neutron group structure of the 260-group data set is reported in Table 10.1. The corresponding gamma 42-group structure is reported in Table 10.2.

|cc|cc|cc|cc|

& & & & & & &   & & & & & & &
& & & & & & &
& & & & & & &
& & & & & & &   & & & & & & &
& & & & & & &
& & & & & & &
& \(2.000000 \cdot 10^{-2}\) & 2 & \(1.964033 \cdot 10^{-2}\) & 3 & \(1.915541 \cdot 10^{-2}\) & 4 & \(1.868246 \cdot 10^{-2}\)
& \(1.822119 \cdot 10^{-2}\) & 6 & \(1.777131 \cdot 10^{-2}\) & 7 & \(1.733253 \cdot 10^{-2}\) & 8 & \(1.690459 \cdot 10^{-2}\)
& \(1.648721 \cdot 10^{-2}\) & 10 & \(1.608014 \cdot 10^{-2}\) & 11 & \(1.568312 \cdot 10^{-2}\) & 12 & \(1.529590 \cdot 10^{-2}\)
& \(1.491825 \cdot 10^{-2}\) & 14 & \(1.454991 \cdot 10^{-2}\) & 15 & \(1.419068 \cdot 10^{-2}\) & 16 & \(1.384031 \cdot 10^{-2}\)
& \(1.349859 \cdot 10^{-2}\) & 18 & \(1.316531 \cdot 10^{-2}\) & 19 & \(1.284025 \cdot 10^{-2}\) & 20 & \(1.252323 \cdot 10^{-2}\)
& \(1.221403 \cdot 10^{-2}\) & 22 & \(1.191246 \cdot 10^{-2}\) & 23 & \(1.161834 \cdot 10^{-2}\) & 24 & \(1.133148 \cdot 10^{-2}\)
& \(1.105171 \cdot 10^{-2}\) & 26 & \(1.077884 \cdot 10^{-2}\) & 27 & \(1.051271 \cdot 10^{-2}\) & 28 & \(1.025315 \cdot 10^{-2}\)
& \(1.000000 \cdot 10^{-2}\) & 30 & \(9.753099 \cdot 10^{-3}\) & 31 & \(9.512294 \cdot 10^{-3}\) & 32 & \(9.277435 \cdot 10^{-3}\)
& \(9.048374 \cdot 10^{-3}\) & 34 & \(8.824969 \cdot 10^{-3}\) & 35 & \(8.607080 \cdot 10^{-3}\) & 36 & \(8.394570 \cdot 10^{-3}\)
& \(8.187308 \cdot 10^{-3}\) & 38 & \(7.985162 \cdot 10^{-3}\) & 39 & \(7.788008 \cdot 10^{-3}\) & 40 & \(7.595721 \cdot 10^{-3}\)
& \(7.408182 \cdot 10^{-3}\) & 42 & \(7.225274 \cdot 10^{-3}\) & 43 & \(7.046881 \cdot 10^{-3}\) & 44 & \(6.872893 \cdot 10^{-3}\)
& \(6.703200 \cdot 10^{-3}\) & 46 & \(6.647595 \cdot 10^{-3}\) & 47 & \(6.592384 \cdot 10^{-3}\) & 48 & \(6.537698 \cdot 10^{-3}\)
& \(6.376282 \cdot 10^{-3}\) & 50 & \(6.218851 \cdot 10^{-3}\) & 51 & \(6.065307 \cdot 10^{-3}\) & 52 & \(5.915554 \cdot 10^{-3}\)
& \(5.769498 \cdot 10^{-3}\) & 54 & \(5.488116 \cdot 10^{-3}\) & 55 & \(5.220458 \cdot 10^{-3}\) & 56 & \(4.965853 \cdot 10^{-3}\)
& \(4.843246 \cdot 10^{-3}\) & 58 & \(4.723666 \cdot 10^{-3}\) & 59 & \(4.607038 \cdot 10^{-3}\) & 60 & \(4.493290 \cdot 10^{-3}\)
& \(4.274149 \cdot 10^{-3}\) & 62 & \(4.065697 \cdot 10^{-3}\) & 63 & \(3.867410 \cdot 10^{-3}\) & 64 & \(3.678794 \cdot 10^{-3}\)
& \(3.499377 \cdot 10^{-3}\) & 66 & \(3.328711 \cdot 10^{-3}\) & 67 & \(3.246525 \cdot 10^{-3}\) & 68 & \(3.166368 \cdot 10^{-3}\)
& \(3.088190 \cdot 10^{-3}\) & 70 & \(3.011942 \cdot 10^{-3}\) & 71 & \(2.865048 \cdot 10^{-3}\) & 72 & \(2.725318 \cdot 10^{-3}\)
& \(2.592403 \cdot 10^{-3}\) & 74 & \(2.465970 \cdot 10^{-3}\) & 75 & \(2.425130 \cdot 10^{-3}\) & 76 & \(2.385205 \cdot 10^{-3}\)
& \(2.365253 \cdot 10^{-3}\) & 78 & \(2.345703 \cdot 10^{-3}\) & 79 & \(2.306855 \cdot 10^{-3}\) & 80 & \(2.268877 \cdot 10^{-3}\)
& \(2.231302 \cdot 10^{-3}\) & 82 & \(2.122480 \cdot 10^{-3}\) & 83 & \(2.018965 \cdot 10^{-3}\) & 84 & \(1.969117 \cdot 10^{-3}\)
& \(1.920499 \cdot 10^{-3}\) & 86 & \(1.873082 \cdot 10^{-3}\) & 87 & \(1.826835 \cdot 10^{-3}\) & 88 & \(1.737739 \cdot 10^{-3}\)
& \(1.652989 \cdot 10^{-3}\) & 90 & \(1.612176 \cdot 10^{-3}\) & 91 & \(1.572372 \cdot 10^{-3}\) & 92 & \(1.533550 \cdot 10^{-3}\)
& \(1.495686 \cdot 10^{-3}\) & 94 & \(1.422741 \cdot 10^{-3}\) & 95 & \(1.353353 \cdot 10^{-3}\) & 96 & \(1.287349 \cdot 10^{-3}\)
& \(1.224564 \cdot 10^{-3}\) & 98 & \(1.194330 \cdot 10^{-3}\) & 99 & \(1.164842 \cdot 10^{-3}\) & 100 & \(1.108032 \cdot 10^{-3}\)
& \(1.053992 \cdot 10^{-3}\) & 102 & \(1.002588 \cdot 10^{-3}\) & 103 & \(9.778344 \cdot 10^{-4}\) & 104 & \(9.616402 \cdot 10^{-4}\)
& \(9.536916 \cdot 10^{-4}\) & 106 & \(9.071795 \cdot 10^{-4}\) & 107 & \(8.629359 \cdot 10^{-4}\) & 108 & \(8.208500 \cdot 10^{-4}\)
& \(7.808167 \cdot 10^{-4}\) & 110 & \(7.427358 \cdot 10^{-4}\) & 111 & \(7.065121 \cdot 10^{-4}\) & 112 & \(6.720551 \cdot 10^{-4}\)
& \(6.392786 \cdot 10^{-4}\) & 114 & \(6.081006 \cdot 10^{-4}\) & 115 & \(5.784432 \cdot 10^{-4}\) & 116 & \(5.502322 \cdot 10^{-4}\)
& \(5.366469 \cdot 10^{-4}\) & 118 & \(5.233971 \cdot 10^{-4}\) & 119 & \(5.104743 \cdot 10^{-4}\) & 120 & \(4.978707 \cdot 10^{-4}\)
& \(4.735892 \cdot 10^{-4}\) & 122 & \(4.504920 \cdot 10^{-4}\) & 123 & \(4.285213 \cdot 10^{-4}\) & 124 & \(4.076220 \cdot 10^{-4}\)
& \(3.877421 \cdot 10^{-4}\) & 126 & \(3.688317 \cdot 10^{-4}\) & 127 & \(3.508435 \cdot 10^{-4}\) & 128 & \(3.337327 \cdot 10^{-4}\)
& \(3.174564 \cdot 10^{-4}\) & 130 & \(3.096183 \cdot 10^{-4}\) & 131 & \(3.019738 \cdot 10^{-4}\) & 132 & \(2.945181 \cdot 10^{-4}\)
& \(2.872464 \cdot 10^{-4}\) & 134 & \(2.801543 \cdot 10^{-4}\) & 135 & \(2.732372 \cdot 10^{-4}\) & 136 & \(2.599113 \cdot 10^{-4}\)
& \(2.472353 \cdot 10^{-4}\) & 138 & \(2.351775 \cdot 10^{-4}\) & 139 & \(2.237077 \cdot 10^{-4}\) & 140 & \(2.127974 \cdot 10^{-4}\)
& \(2.024191 \cdot 10^{-4}\) & 142 & \(1.925470 \cdot 10^{-4}\) & 143 & \(1.831564 \cdot 10^{-4}\) & 144 & \(1.742237 \cdot 10^{-4}\)
& \(1.699221 \cdot 10^{-4}\) & 146 & \(1.657268 \cdot 10^{-4}\) & 147 & \(1.616349 \cdot 10^{-4}\) & 148 & \(1.576442 \cdot 10^{-4}\)
& \(1.499558 \cdot 10^{-4}\) & 150 & \(1.426423 \cdot 10^{-4}\) & 151 & \(1.356856 \cdot 10^{-4}\) & 152 & \(1.290681 \cdot 10^{-4}\)
& \(1.227734 \cdot 10^{-4}\) & 154 & \(1.167857 \cdot 10^{-4}\) & 155 & \(1.110900 \cdot 10^{-4}\) & 156 & \(9.803655 \cdot 10^{-5}\)
& \(8.651695 \cdot 10^{-5}\) & 158 & \(7.635094 \cdot 10^{-5}\) & 159 & \(6.737947 \cdot 10^{-5}\) & 160 & \(6.251086 \cdot 10^{-5}\)
& \(5.946217 \cdot 10^{-5}\) & 162 & \(5.656217 \cdot 10^{-5}\) & 163 & \(5.247518 \cdot 10^{-5}\) & 164 & \(4.630919 \cdot 10^{-5}\)
& \(4.086771 \cdot 10^{-5}\) & 166 & \(3.606563 \cdot 10^{-5}\) & 167 & \(3.517517 \cdot 10^{-5}\) & 168 & \(3.430669 \cdot 10^{-5}\)
& \(3.182781 \cdot 10^{-5}\) & 170 & \(2.808794 \cdot 10^{-5}\) & 171 & \(2.605841 \cdot 10^{-5}\) & 172 & \(2.478752 \cdot 10^{-5}\)
& \(2.417552 \cdot 10^{-5}\) & 174 & \(2.357862 \cdot 10^{-5}\) & 175 & \(2.187491 \cdot 10^{-5}\) & 176 & \(2.133482 \cdot 10^{-5}\)
& \(1.930454 \cdot 10^{-5}\) & 178 & \(1.703620 \cdot 10^{-5}\) & 179 & \(1.503439 \cdot 10^{-5}\) & 180 & \(1.326780 \cdot 10^{-5}\)
& \(1.170880 \cdot 10^{-5}\) & 182 & \(1.033298 \cdot 10^{-5}\) & 183 & \(9.118820 \cdot 10^{-6}\) & 184 & \(8.047330 \cdot 10^{-6}\)
& \(7.101744 \cdot 10^{-6}\) & 186 & \(6.267267 \cdot 10^{-6}\) & 187 & \(5.530844 \cdot 10^{-6}\) & 188 & \(5.004514 \cdot 10^{-6}\)
& \(4.528272 \cdot 10^{-6}\) & 190 & \(4.307425 \cdot 10^{-6}\) & 191 & \(4.097350 \cdot 10^{-6}\) & 192 & \(3.707435 \cdot 10^{-6}\)
& \(3.354626 \cdot 10^{-6}\) & 194 & \(3.035391 \cdot 10^{-6}\) & 195 & \(2.863488 \cdot 10^{-6}\) & 196 & \(2.746536 \cdot 10^{-6}\)
& \(2.612586 \cdot 10^{-6}\) & 198 & \(2.485168 \cdot 10^{-6}\) & 199 & \(2.248673 \cdot 10^{-6}\) & 200 & \(2.034684 \cdot 10^{-6}\)
& \(1.841058 \cdot 10^{-6}\) & 202 & \(1.665858 \cdot 10^{-6}\) & 203 & \(1.584613 \cdot 10^{-6}\) & 204 & \(1.507331 \cdot 10^{-6}\)
& \(1.363889 \cdot 10^{-6}\) & 206 & \(1.234098 \cdot 10^{-6}\) & 207 & \(9.611165 \cdot 10^{-7}\) & 208 & \(7.485183 \cdot 10^{-7}\)
& \(5.829466 \cdot 10^{-7}\) & 210 & \(4.539993 \cdot 10^{-7}\) & 211 & \(3.535750 \cdot 10^{-7}\) & 212 & \(2.753645 \cdot 10^{-7}\)
& \(2.144541 \cdot 10^{-7}\) & 214 & \(1.670170 \cdot 10^{-7}\) & 215 & \(1.300730 \cdot 10^{-7}\) & 216 & \(1.013009 \cdot 10^{-7}\)
& \(7.889325 \cdot 10^{-8}\) & 218 & \(6.144212 \cdot 10^{-8}\) & 219 & \(4.785117 \cdot 10^{-8}\) & 220 & \(3.726653 \cdot 10^{-8}\)  221 & \(2.902320 \cdot 10^{-8}\) & 222 & \(2.260329 \cdot 10^{-8}\) & 223 & \(1.760346 \cdot 10^{-8}\) & 224 & \(1.370959 \cdot 10^{-8}\)
& \(1.067704 \cdot 10^{-8}\) & 226 & \(8.315287 \cdot 10^{-9}\) & 227 & \(6.475952 \cdot 10^{-9}\) & 228 & \(5.043477 \cdot 10^{-9}\)  229 & \(3.927864 \cdot 10^{-9}\) &
& \(3.059023 \cdot 10^{-9}\) & 231 & \(2.382370 \cdot 10^{-9}\) & 232 & \(1.855391 \cdot 10^{-9}\) & 233 & \(1.444980 \cdot 10^{-9}\)
& \(1.125352 \cdot 10^{-9}\) & 235 & \(8.764248 \cdot 10^{-10}\) & 236 & \(8.336811 \cdot 10^{-10}\) & 237 & \(6.825603 \cdot 10^{-10}\)
& \(6.250621 \cdot 10^{-10}\) & 239 & \(5.315785 \cdot 10^{-10}\) & 240 & \(4.139938 \cdot 10^{-10}\) & 241 & \(2.826153 \cdot 10^{-10}\)
& \(1.929290 \cdot 10^{-10}\) & 243 & \(1.317041 \cdot 10^{-10}\) & 244 & \(8.990856 \cdot 10^{-11}\) & 245 & \(6.137660 \cdot 10^{-11}\)
& \(4.189910 \cdot 10^{-11}\) & 247 & \(2.860266 \cdot 10^{-11}\) & 248 & \(1.952578 \cdot 10^{-11}\) & 249 & \(1.332938 \cdot 10^{-11}\)
& \(9.099382 \cdot 10^{-12}\) & 251 & \(6.211746 \cdot 10^{-12}\) & 252 & \(4.240485 \cdot 10^{-12}\) & 253 & \(2.894792 \cdot 10^{-12}\)
& \(1.976147 \cdot 10^{-12}\) & 255 & \(1.349028 \cdot 10^{-12}\) & 256 & \(9.209218 \cdot 10^{-13}\) & 257 & \(6.286727 \cdot 10^{-13}\)
& \(4.291671 \cdot 10^{-13}\) & 259 & \(2.929734 \cdot 10^{-13}\) & 260 & \(2.000000 \cdot 10^{-13}\) & &

|cc|cc|cc|cc|

& & & & & & &   & & & & & & &
& & & & & & &
& & & & & & &
& & & & & & &   & & & & & & &
& & & & & & &
& & & & & & &
1 & \(5.000000 \cdot 10^{-2}\) & 2 & \(3.000000 \cdot 10^{-2}\) & 3 & \(2.000000 \cdot 10^{-2}\) & 4 & \(1.400000 \cdot 10^{-2}\)
5 & \(1.200000 \cdot 10^{-2}\) & 6 & \(1.000000 \cdot 10^{-2}\) & 7 & \(8.000000 \cdot 10^{-3}\) & 8 & \(7.500000 \cdot 10^{-3}\)
9 & \(7.000000 \cdot 10^{-3}\) & 10 & \(6.500000 \cdot 10^{-3}\) & 11 & \(6.000000 \cdot 10^{-3}\) & 12 & \(5.500000 \cdot 10^{-3}\)
13 & \(5.000000 \cdot 10^{-3}\) & 14 & \(4.500000 \cdot 10^{-3}\) & 15 & \(4.000000 \cdot 10^{-3}\) & 16 & \(3.500000 \cdot 10^{-3}\)
17 & \(3.000000 \cdot 10^{-3}\) & 18 & \(2.500000 \cdot 10^{-3}\) & 19 & \(2.000000 \cdot 10^{-3}\) & 20 & \(1.660000 \cdot 10^{-3}\)
21 & \(1.500000 \cdot 10^{-3}\) & 22 & \(1.340000 \cdot 10^{-3}\) & 23 & \(1.330000 \cdot 10^{-3}\) & 24 & \(1.000000 \cdot 10^{-3}\)
25 & \(8.000000 \cdot 10^{-4}\) & 26 & \(7.000000 \cdot 10^{-4}\) & 27 & \(6.000000 \cdot 10^{-4}\) & 28 & \(5.120000 \cdot 10^{-4}\)
29 & \(5.100000 \cdot 10^{-4}\) & 30 & \(4.500000 \cdot 10^{-4}\) & 31 & \(4.000000 \cdot 10^{-4}\) & 32 & \(3.000000 \cdot 10^{-4}\)
33 & \(2.000000 \cdot 10^{-4}\) & 34 & \(1.500000 \cdot 10^{-4}\) & 35 & \(1.000000 \cdot 10^{-4}\) & 36 & \(7.500000 \cdot 10^{-5}\)
37 & \(7.000000 \cdot 10^{-5}\) & 38 & \(6.000000 \cdot 10^{-5}\) & 39 & \(4.500000 \cdot 10^{-5}\) & 40 & \(3.000000 \cdot 10^{-5}\)
41 & \(2.000000 \cdot 10^{-5}\) & 42 & \(1.000000 \cdot 10^{-5}\) &

New group library: Available materials¶

A list of the materials for which cross sections are available in the new 260-group library is reported in Table 10.3. The different columns of the Table contain, in the order:

the symbol of the nuclide (if the atomic mass number is not present, the cross sections refer to the natural element composition)
a short description of the material
the temperature in degrees Kelvin at which the cross sections have been processed
the evaluated data file (origin) from which the data are derived
the availability of information on production of residual nuclei
the name with which FLUKA refers to that material
the first numerical identifier of the material
the second numerical identifier of the material
the third numerical identifier of the material
the availability of information on gamma production

@rlrlllrrrl@

& & & & & & & & &
& & & & & & & &
& & & & & & &
& & & & & & & & &
& & & & & & & &
& & & & & & &
H & H\(_2\)O bound nat. Hydrogen & 296 & ENDF/B–VIIR0 & Yes & HYDROGEN & 1 & -2 & 296 & Yes  H & CH\(_2\) bound nat. Hydrogen & 296 & ENDF/B–VIIR0 & Yes & HYDROGEN & 1 & -3 & 296 & Yes  H & Free gas natural Hydrogen & 296 & ENDF/B–VIIR0 & Yes & HYDROGEN & 1 & -5 & 296 & Yes  H & Free gas natural Hydrogen & 87 & ENDF/B–VIIR0 & Yes & HYDROGEN & 1 & -2 & 87 & Yes  H & Free gas natural Hydrogen & 4 & ENDF/B–VIIR0 & Yes & HYDROGEN & 1 & -5 & 4 & Yes
H & Free gas natural Hydrogen & 430 & ENDF/B–VIIR0 & Yes & HYDROGEN & 1 & -5 & 430 & Yes
\(^1\)H & H\(_2\)O bound Hydrogen 1 & 296 & ENDF/B–VIIR0 & Yes & HYDROG-1 & 1 & +1 & 296 & Yes  \(^1\)H & CH\(_2\) bound Hydrogen 1 & 296 & ENDF/B–VIIR0 & Yes & HYDROG-1 & 1 & +11 & 296 & Yes  \(^1\)H & Free gas Hydrogen 1 & 296 & ENDF/B–VIIR0 & Yes & HYDROG-1 & 1 & +31 & 296 & Yes  \(^1\)H & Free gas Hydrogen 1 & 87 & ENDF/B–VIIR0 & Yes & HYDROG-1 & 1 & +1 & 87 & Yes  \(^2\)H & D2O bound Deuterium & 296 & ENDF/B–VIIR0 & Yes & DEUTERIU & 1 & +2 & 296 & Yes  \(^2\)H & Free gas Deuterium & 296 & ENDF/B–VIIR0 & Yes & DEUTERIU & 1 & +32 & 296 & Yes  \(^2\)H & Free gas Deuterium & 87 & ENDF/B–VIIR0 & Yes & DEUTERIU & 1 & +2 & 87 & Yes  \(^3\)H & Free gas Tritium & 296 & ENDF/B–VIIR0 & Yes & TRITIUM & 1 & +4 & 296 & Yes  \(^3\)H & Free gas Tritium & 87 & ENDF/B–VIIR0 & Yes & TRITIUM & 1 & +4 & 87 & Yes  He & Natural Helium & 296 & ENDF/B–VIIR0 & Yes & HELIUM & 2 & -2 & 296 & Yes  He & Natural Helium & 87 & ENDF/B–VIIR0 & Yes & HELIUM & 2 & -2 & 87 & Yes  He & Natural Helium & 4 & ENDF/B–VIIR0 & Yes & HELIUM & 2 & -2 & 4 & Yes  \(^3\)He & Helium 3 & 296 & ENDF/B–VIIR0 & Yes & HELIUM-3 & 2 & +3 & 296 & Yes  \(^3\)He & Helium 3 & 87 & ENDF/B–VIIR0 & Yes & HELIUM-3 & 2 & +3 & 87 & Yes  \(^3\)He & Helium 3 & 4 & ENDF/B–VIIR0 & Yes & HELIUM-3 & 2 & +3 & 4 & Yes  \(^4\)He & Helium 4 & 296 & ENDF/B–VIIR0 & Yes & HELIUM-4 & 2 & +4 & 296 & Yes  \(^4\)He & Helium 4 & 87 & ENDF/B–VIIR0 & Yes & HELIUM-4 & 2 & +4 & 87 & Yes  \(^4\)He & Helium 4 & 4 & ENDF/B–VIIR0 & Yes & HELIUM-4 & 2 & +4 & 4 & Yes  Li & Natural Lithium & 296 & ENDF/B–VIIIR0 & Yes & LITHIUM & 3 & -2 & 296 & Yes  Li & Natural Lithium & 87 & ENDF/B–VIIIR0 & Yes & LITHIUM & 3 & -2 & 87 & Yes  \(^6\)Li & Lithium 6 & 296 & ENDF/B–VIIIR0 & Yes & LITHIU-6 & 3 & +6 & 296 & Yes  \(^6\)Li & Lithium 6 & 87 & ENDF/B–VIIIR0 & Yes & LITHIU-6 & 3 & +6 & 87 & Yes  \(^7\)Li & Lithium 7 & 296 & ENDF/B–VIIIR0 & Yes & LITHIU-7 & 3 & +7 & 296 & Yes  \(^7\)Li & Lithium 7 & 87 & ENDF/B–VIIIR0 & Yes & LITHIU-7 & 3 & +7 & 87 & Yes  \(^9\)Be & Beryllium 9 & 296 & ENDF/B–VIIIR0 & Yes & BERYLLIU & 4 & +9 & 296 & Yes  \(^9\)Be & Beryllium 9 & 87 & ENDF/B–VIIIR0 & Yes & BERYLLIU & 4 & +9 & 87 & Yes  B & Natural Boron & 296 & ENDF/B–VIIIR0 & Yes & BORON & 5 & -2 & 296 & Yes  B & Natural Boron & 87 & ENDF/B–VIIIR0 & Yes & BORON & 5 & -2 & 87 & Yes  \(^{10}\)B & Boron 10 & 296 & JENDL–4.0 & Yes & BORON-10 & 5 & +10 & 296 & Yes  \(^{10}\)B & Boron 10 & 87 & JENDL–4.0 & Yes & BORON-10 & 5 & +10 & 87 & Yes  \(^{11}\)B & Boron 11 & 296 & ENDF/B–VIIIR0 & Yes & BORON-11 & 5 & +11 & 296 & Yes  \(^{11}\)B & Boron 11 & 87 & ENDF/B–VIIIR0 & Yes & BORON-11 & 5 & +11 & 87 & Yes  C & Free gas natural Carbon & 296 & ENDF/B–VIIIR0 & Yes & CARBON & 6 & -2 & 296 & Yes  C & Free gas natural Carbon & 87 & ENDF/B–VIIIR0 & Yes & CARBON & 6 & -2 & 87 & Yes  C & Free gas natural Carbon & 4 & ENDF/B–VIIIR0 & Yes & CARBON & 6 & -2 & 4 & Yes
C & Free gas natural Carbon & 430 & ENDF/B–VIIIR0 & Yes & CARBON & 6 & -2 & 430 & Yes
C & Graphite bound natural Carbon & 296 & ENDF/B–VIIIR0 & Yes & CARBON & 6 & -3 & 296 & Yes  \(^{12}\)C & Carbon 12 & 296 & ENDF/B–VIIIR0 & Yes & CARBON & 6 & 12 & 296 & Yes
\(^{12}\)C & Carbon 12 & 87 & ENDF/B–VIIIR0 & Yes & CARBON & 6 & 12 & 87 & Yes
N & Natural Nitrogen & 296 & ENDF/B–VIIIR0 & Yes & NITROGEN & 7 & -2 & 296 & Yes  N & Natural Nitrogen & 87 & ENDF/B–VIIIR0 & Yes & NITROGEN & 7 & -2 & 87 & Yes  \(^{14}\)N & Nitrogen 14 & 296 & ENDF/B–VIIIR0 & Yes & NITRO-14 & 7 & +14 & 296 & Yes  \(^{14}\)N & Nitrogen 14 & 87 & ENDF/B–VIIIR0 & Yes & NITRO-14 & 7 & +14 & 87 & Yes  O & Natural Oxygen & 296 & ENDF/B–VIIIR0 & Yes & OXYGEN & 8 & -2 & 296 & Yes  O & Natural Oxygen & 87 & ENDF/B–VIIIR0 & Yes & OXYGEN & 8 & -2 & 87 & Yes  O & Natural Oxygen & 4 & ENDF/B–VIIIR0 & Yes & OXYGEN & 8 & -2 & 4 & Yes
O & Natural Oxygen & 430 & ENDF/B–VIIIR0 & Yes & OXYGEN & 8 & -2 & 430 & Yes
\(^{16}\)O & Oxygen 16 & 296 & ENDF/B–VIIIR0 & Yes & OXYGE-16 & 8 & +16 & 296 & Yes  \(^{16}\)O & Oxygen 16 & 87 & ENDF/B–VIIIR0 & Yes & OXYGE-16 & 8 & +16 & 87 & Yes  \(^{19}\)F & Fluorine 19 & 296 & ENDF/B–VIIIR0 & Yes & FLUORINE & 9 & +19 & 296 & Yes  \(^{19}\)F & Fluorine 19 & 87 & ENDF/B–VIIIR0 & Yes & FLUORINE & 9 & +19 & 87 & Yes  Ne & Natural Neon & 296 & TENDL–19 & Yes & NEON & 10 & -2 & 296 & Yes
\(^{23}\)Na & Sodium 23 & 296 & ENDF/B–VIIIR0 & Yes & SODIUM & 11 & +23 & 296 & Yes  \(^{23}\)Na & Sodium 23 & 87 & ENDF/B–VIIIR0 & Yes & SODIUM & 11 & +23 & 87 & Yes  Mg & Natural Magnesium & 296 & ENDF/B–VIIIR0 & Yes & MAGNESIU & 12 & -2 & 296 & Yes  Mg & Natural Magnesium & 87 & ENDF/B–VIIIR0 & Yes & MAGNESIU & 12 & -2 & 87 & Yes  \(^{27}\)Al & Aluminium 27 & 296 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & +27 & 296 & Yes  \(^{27}\)Al & Aluminium 27 & 87 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & +27 & 87 & Yes  \(^{27}\)Al & Aluminium 27 & 4 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & +27 & 4 & Yes  \(^{27}\)Al & Aluminium 27 & 430 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & +27 & 430 & Yes
\(^{27}\)Al & Aluminium 27 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & 1027 & 296 & Yes
\(^{27}\)Al & Aluminium 27 SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & 1027 & 87 & Yes
\(^{27}\)Al & Aluminium 27 SelfShielded & 4 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & 1027 & 4 & Yes
\(^{27}\)Al & Aluminium 27 SelfShielded & 430 & ENDF/B–VIIIR0 & Yes & ALUMINUM & 13 & 1027 & 430 & Yes
Si & Natural Silicon & 296 & ENDF/B–VIIIR0 & Yes & SILICON & 14 & -2 & 296 & Yes  Si & Natural Silicon & 87 & ENDF/B–VIIIR0 & Yes & SILICON & 14 & -2 & 87 & Yes
\(^{28}\)Si & Silicon 28 & 296 & ENDF/B–VIIIR0 & Yes & SILIC-28 & 14 & +28 & 296 & Yes
\(^{28}\)Si & Silicon 28 & 87 & ENDF/B–VIIIR0 & Yes & SILIC-28 & 14 & +28 & 87 & Yes
\(^{31}\)P & Phosphorus 31 & 296 & ENDF/B–VIIIR0 & Yes & PHOSPHO & 15 & 31 & 296 & Yes
\(^{31}\)P & Phosphorus 31 & 87 & ENDF/B–VIIIR0 & Yes & PHOSPHO & 15 & 31 & 87 & Yes
S & Natural Sulphur\(^{\,(1)}\) & 296 & JENDL–3.3 & Yes & SULFUR & 16 & -2 & 296 & Yes
S & Natural Sulphur\(^{\,(1)}\) & 87 & JENDL–3.3 & Yes & SULFUR & 16 & -2 & 87 & Yes
Cl & Natural Chlorine & 296 & ENDF/B–VIIR0 & Yes & CHLORINE & 17 & -2 & 296 & Yes
Cl & Natural Chlorine & 87 & ENDF/B–VIIR0 & Yes & CHLORINE & 17 & -2 & 87 & Yes
Ar & Natural Argon & 296 & ENDF/B–VIIIR0 & Yes & ARGON & 18 & -2 & 296 & Yes
Ar & Natural Argon & 87 & ENDF/B–VIIIR0 & Yes & ARGON & 18 & -2 & 87 & Yes
Ar & Natural Argon SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & ARGON & 18 & -4 & 296 & Yes
Ar & Natural Argon SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & ARGON & 18 & -4 & 87 & Yes
\(^{40}\)Ar & Argon 40 & 296 & ENDF/B–VIIIR0 & Yes & ARGON-40 & 18 & 40 & 296 & Yes
\(^{40}\)Ar & Argon 40 & 87 & ENDF/B–VIIIR0 & Yes & ARGON-40 & 18 & 40 & 87 & Yes
\(^{40}\)Ar & Argon 40 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & ARGON-40 & 18 & 1040 & 296 & Yes
\(^{40}\)Ar & Argon 40 SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & ARGON-40 & 18 & 1040 & 87 & Yes
K & Natural Potassium & 296 & ENDF/B–VIIR1 & Yes & POTASSIU & 19 & -2 & 296 & Yes
K & Natural Potassium & 87 & ENDF/B–VIIR1 & Yes & POTASSIU & 19 & -2 & 87 & Yes
Ca & Natural Calcium\(^{\,(2)}\) & 296 & ENDF/B–VIIR0 & Yes & CALCIUM & 20 & -2 & 296 & Yes
Ca & Natural Calcium\(^{\,(2)}\) & 87 & ENDF/B–VIIR0 & Yes & CALCIUM & 20 & -2 & 87 & Yes
\(^{45}\)Sc & Scandium 45\(^{\,(2)}\) & 296 & ENDF/B-VIIR0 & Yes & SCANDIUM & 21 & 45 & 296 & Yes
\(^{45}\)Sc & Scandium 45\(^{\,(2)}\) & 87 & ENDF/B-VIIR0 & Yes & SCANDIUM & 21 & 45 & 87 & Yes
Ti & Natural Titanium & 296 & ENDF/B–VIIR1 & Yes & TITANIUM & 22 & -2 & 296 & Yes  Ti & Natural Titanium & 87 & ENDF/B–VIIR1 & Yes & TITANIUM & 22 & -2 & 87 & Yes  V & Natural Vanadium & 296 & ENDF/B–VIIIR0 & Yes & VANADIUM & 23 & -2 & 296 & Yes  V & Natural Vanadium & 87 & ENDF/B–VIIIR0 & Yes & VANADIUM & 23 & -2 & 87 & Yes  Cr & Natural Chromium & 296 & ENDF/B–VIIR1 & Yes & CHROMIUM & 24 & -2 & 296 & Yes  Cr & Natural Chromium & 87 & ENDF/B–VIIR1 & Yes & CHROMIUM & 24 & -2 & 87 & Yes  Cr & Natural Chromium & 4 & ENDF/B–VIIR1 & Yes & CHROMIUM & 24 & -2 & 4 & Yes
Cr & Natural Chromium & 430 & ENDF/B–VIIR1 & Yes & CHROMIUM & 24 & -2 & 430 & Yes
\(^{55}\)Mn & Manganese 55 & 296 & ENDF/B–VIIIR0 & Yes & MANGANES & 25 & 55 & 296 & Yes  \(^{55}\)Mn & Manganese 55 & 87 & ENDF/B–VIIIR0 & Yes & MANGANES & 25 & 55 & 87 & Yes  \(^{55}\)Mn & Manganese 55 & 4 & ENDF/B–VIIIR0 & Yes & MANGANES & 25 & 55 & 4 & Yes
\(^{55}\)Mn & Manganese 55 & 430 & ENDF/B–VIIIR0 & Yes & MANGANES & 25 & 55 & 430 & Yes
\(^{55}\)Mn & Manganese 55 SelfShielded & 296 & ENDF/B–VIIIR0 &Yes & MANGANES & 25 & 1055 & 296 & Yes  Fe & Natural Iron & 296 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -2 & 296 & Yes  Fe & Natural Iron & 87 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -2 & 87 & Yes  Fe & Natural Iron & 4 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -2 & 4 & Yes
Fe & Natural Iron & 430 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -2 & 430 & Yes
Fe & Natural Iron SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -4 & 296 & Yes  Fe & Natural Iron SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -4 & 87 & Yes  Fe & Natural Iron SelfShielded & 4 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -4 & 4 & Yes
Fe & Natural Iron SelfShielded & 430 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -4 & 430 & Yes
Fe & Shielding Fe (5% C) SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -8 & 296 & Yes  Fe & Shielding Fe (5% C) SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -8 & 87 & Yes  Fe & Shielding Fe (5% C) SelfShielded & 4 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -8 & 4 & Yes
Fe & Shielding Fe (5% C) SelfShielded & 430 & ENDF/B–VIIIR0 & Yes & IRON & 26 & -8 & 430 & Yes
Fe & Natural Iron & 296 & ENDF/B–VIIR1 & Yes & IRON & 26 & -712 & 296 & Yes
Fe & Natural Iron SelfShielded & 296 & ENDF/B–VIIR1 & Yes & IRON & 26 & -714 & 296 & Yes  \(^{56}\)Fe & Iron 56 & 296 & ENDF/B–VIIIR0 & Yes & 56-FE & 26 & 56 & 296 & Yes
\(^{56}\)Fe & Iron 56 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & 56-FE & 26 & 1056 & 296 & Yes  \(^{59}\)Co & Cobalt 59 & 296 & ENDF/B–VIIIR0 & Yes & COBALT & 27 & 59 & 296 & Yes
\(^{59}\)Co & Cobalt 59 & 87 & ENDF/B–VIIIR0 & Yes & COBALT & 27 & 59 & 87 & Yes
\(^{59}\)Co & Cobalt 59 & 4 & ENDF/B–VIIIR0 & Yes & COBALT & 27 & 59 & 4 & Yes
\(^{59}\)Co & Cobalt 59 & 430 & ENDF/B–VIIIR0 & Yes & COBALT & 27 & 59 & 430 & Yes
\(^{59}\)Co & Cobalt 59 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & COBALT & 27 & 1059 & 296 & Yes
Ni & Natural Nickel & 296 & ENDF/B–VIIIR0 & Yes & NICKEL & 28 & -2 & 296 & Yes
Ni & Natural Nickel & 87 & ENDF/B–VIIIR0 & Yes & NICKEL & 28 & -2 & 87 & Yes
Ni & Natural Nickel & 4 & ENDF/B–VIIIR0 & Yes & NICKEL & 28 & -2 & 4 & Yes
Ni & Natural Nickel & 430 & ENDF/B–VIIIR0 & Yes & NICKEL & 28 & -2 & 430 & Yes
Ni & Natural Nickel SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & NICKEL & 28 & -4 & 296 & Yes
Ni & Natural Nickel & 296 & ENDF/B–VIIR1 & Yes & NICKEL & 28 & -712 & 296 & Yes
Cu & Natural Copper & 296 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -2 & 296 & Yes  Cu & Natural Copper & 87 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -2 & 87 & Yes  Cu & Natural Copper & 4 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -2 & 4 & Yes  Cu & Natural Copper & 430 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -2 & 430 & Yes
Cu & Natural Copper SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -4 & 296 & Yes  Cu & Natural Copper SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -4 & 87 & Yes  Cu & Natural Copper SelfShielded & 4 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -4 & 4 & Yes  Cu & Natural Copper SelfShielded & 430 & ENDF/B–VIIIR0 & Yes & COPPER & 29 & -4 & 430 & Yes
Zn & Natural Zinc & 296 & JENDL–4.0 & Yes & ZINC & 30 & -2 & 296 & Yes
Zn & Natural Zinc & 87 & JENDL–4.0 & Yes & ZINC & 30 & -2 & 87 & Yes
Zn & Natural Zinc & 4 & JENDL–4.0 & Yes & ZINC & 30 & -2 & 4 & Yes
Zn & Natural Zinc & 430 & JENDL–4.0 & Yes & ZINC & 30 & -2 & 430 & Yes
Ga & Natural Gallium & 296 & JEFF–3.2 & Yes & GALLIUM & 31 & -2 & 296 & Yes  Ga & Natural Gallium & 87 & JEFF–3.2 & Yes & GALLIUM & 31 & -2 & 87 & Yes  Ge & Natural Germanium & 296 & ENDF/B–VIIIR0 & Yes & GERMANIU & 32 & -2 & 296 & Yes
Ge & Natural Germanium & 87 & ENDF/B–VIIIR0 & Yes & GERMANIU & 32 & -2 & 87 & Yes
\(^{75}\)As & Arsenic 75 & 296 & ENDF/B–VIIR1 & Yes & ARSENIC & 33 & 75 & 296 & Yes
\(^{75}\)As & Arsenic 75 & 87 & ENDF/B–VIIR1 & Yes & ARSENIC & 33 & 75 & 87 & Yes
Se & Natural Selenium\(^{\,(2)}\) & 296 & ENDF/B–VIIIR0 & Yes & SELENIUM & 34 & -2 & 296 & No
Br & Natural Bromine & 296 & JEFF–3.2 & Yes & BROMINE & 35 & -2 & 296 & Yes
Br & Natural Bromine & 87 & JEFF–3.2 & Yes & BROMINE & 35 & -2 & 87 & Yes
Kr & Natural Krypton & 296 & ENDF/B–VIIR1 & Yes & KRYPTON & 36 & -2 & 296 & No
Kr & Natural Krypton & 120 & ENDF/B–VIIR1 & Yes & KRYPTON & 36 & -2 & 120 & No
Rb & Natural Rubidium\(^{\,(2)}\) & 296 & ENDF/B–VIIIR0 & Yes & RUBIDIUM & 37 & -2 & 296 & No
Sr & Natural Strontium & 296 & JEFF–3.2 & Yes & STRONTIU & 38 & -2 & 296 & No
Sr & Natural Strontium & 87 & JEFF–3.2 & Yes & STRONTIU & 38 & -2 & 87 & No
\(^{90}\)Sr & Strontium 90 & 296 & JEFF–3.2 & Yes & 90-SR & 38 & 90 & 296 & Yes  \(^{90}\)Sr & Strontium 90 & 87 & JEFF–3.2 & Yes & 90-SR & 38 & 90 & 87 & Yes  \(^{89}\)Y & Yttrium 89 & 296 & ENDF/B–VIR8 & Yes & YTTRIUM & 39 & 89 & 296 & No  \(^{89}\)Y & Yttrium 89 & 87 & ENDF/B–VIR8 & Yes & YTTRIUM & 39 & 89 & 87 & No  Zr & Natural Zirconium\(^{\,(2)}\) & 296 & ENDF/B–VIIIR0 & Yes & ZIRCONIU & 40 & -2 & 296 & Yes
Zr & Natural Zirconium\(^{\,(2)}\) & 87 & ENDF/B–VIIIR0 & Yes & ZIRCONIU & 40 & -2 & 87 & Yes
\(^{90}\)Zr & Zirconium 90 & 296K & ENDF/B-VIIIR0 & Yes & 90-ZR & 40 & 90 & 296 & Yes
\(^{91}\)Zr & Zirconium 91\(^{\,(2)}\) & 296K & ENDF/B-VIIIR0 & Yes & 91-ZR & 40 & 91 & 296 & Yes
\(^{92}\)Zr & Zirconium 92\(^{\,(2)}\) & 296K & ENDF/B-VIIIR0 & Yes & 92-ZR & 40 & 92 & 296 & Yes
\(^{94}\)Zr & Zirconium 94\(^{\,(2)}\) & 296K & ENDF/B-VIIIR0 & Yes & 94-ZR & 40 & 94 & 296 & Yes
\(^{96}\)Zr & Zirconium 96\(^{\,(2)}\) & 296K & ENDF/B-VIIIR0 & Yes & 96-ZR & 40 & 96 & 296 & Yes
\(^{93}\)Nb & Niobium 93\(^{\,(2)}\) & 296 & ENDF/B-VIIR0 & Yes & NIOBIUM & 41 & 93 & 296 & Yes
\(^{93}\)Nb & Niobium 93\(^{\,(2)}\) & 87 & ENDF/B-VIIR0 & Yes & NIOBIUM & 41 & 93 & 87 & Yes
Mo & Natural Molybdenum\(^{\,(2)}\) & 296 & TENDL–19 & Yes & MOLYBDEN & 42 & -2 & 296 & Yes
Mo & Natural Molybdenum\(^{\,(2)}\) & 87 & TENDL–19 & Yes & MOLYBDEN & 42 & -2 & 87 & Yes
\(^{92}\)Mo & Molybdenum 92 & 296K & TENDL–19 & Yes & 92-MO & 42 & 92 & 296 & Yes
\(^{94}\)Mo & Molybdenum 94 & 296K & TENDL–19 & Yes & 94-MO & 42 & 94 & 296 & Yes
\(^{95}\)Mo & Molybdenum 95 & 296K & TENDL–19 & Yes & 95-MO & 42 & 95 & 296 & Yes
\(^{96}\)Mo & Molybdenum 96 & 296K & TENDL–19 & Yes & 96-MO & 42 & 96 & 296 & Yes
\(^{97}\)Mo & Molybdenum 97 & 296K & TENDL–19 & Yes & 97-MO & 42 & 97 & 296 & Yes
\(^{98}\)Mo & Molybdenum 98 & 296K & TENDL–19 & Yes & 98-MO & 42 & 98 & 296 & Yes
\(^{100}\)Mo & Molybdenum 100 & 296K & TENDL–19 & Yes & 100-MO & 42 & 100 & 296 & Yes
\(^{99}\)Tc & Technetium 99 & 296 & ENDF/B–VIIR0 & Yes & 99-TC & 43 & 99 & 296 & Yes
\(^{99}\)Tc & Technetium 99 & 87 & ENDF/B–VIIR0 & Yes & 99-TC & 43 & 99 & 87 & Yes
\(^{103}\)Rh & Rhodium 103 & 296 & ENDF/B–VIIIR0 & Yes & RHODIUM & 45 & 103 & 296 & Yes
Pd & Natural Palladium & 296 & ENDF/B–VIIR1 & Yes & PALLADIU & 46 & -2 & 296 & Yes
Pd & Natural Palladium & 87 & ENDF/B–VIIR1 & Yes & PALLADIU & 46 & -2 & 87 & Yes
\(^{102}\)Pd & Palladium 102 & 296 & ENDF/B–VIIR1 & Yes & 102-PD & 46 & 102 & 296 & Yes
\(^{104}\)Pd & Palladium 104 & 296 & ENDF/B–VIIR1 & Yes & 104-PD & 46 & 104 & 296 & Yes
\(^{105}\)Pd & Palladium 105 & 296 & ENDF/B–VIIR1 & Yes & 105-PD & 46 & 105 & 296 & Yes
\(^{106}\)Pd & Palladium 106 & 296 & ENDF/B–VIIR1 & Yes & 106-PD & 46 & 106 & 296 & Yes
\(^{108}\)Pd & Palladium 108 & 296 & ENDF/B–VIIR1 & Yes & 108-PD & 46 & 108 & 296 & Yes
\(^{110}\)Pd & Palladium 110 & 296 & ENDF/B–VIIR1 & Yes & 110-PD & 46 & 110 & 296 & Yes
Ag & Natural Silver & 296 & ENDF/B–VIIR0 & Yes & SILVER & 47 & -2 & 296 & Yes
Ag & Natural Silver & 87 & ENDF/B–VIIR0 & Yes & SILVER & 47 & -2 & 87 & Yes
Cd & Natural Cadmium\(^{\,(2)}\) & 296 & JENDL–4.0 & Yes & CADMIUM & 48 & -2 & 296 & Yes
Cd & Natural Cadmium\(^{\,(2)}\) & 87 & JENDL–4.0 & Yes & CADMIUM & 48 & -2 & 87 & Yes
In & Natural Indium & 296 & TENDL–19 & Yes & INDIUM & 49 & -2 & 296 & Yes
In & Natural Indium SelfShielded & 296 & TENDL–19 & Yes & INDIUM & 49 & -4 & 296 & Yes
In & Natural Indium & 87 & TENDL–19 & Yes & INDIUM & 49 & -2 & 87 & Yes
Sn & Natural Tin & 296 & JENDL–4.0 & Yes & TIN & 50 & -2 & 296 & Yes
Sn & Natural Tin & 87 & JENDL–4.0 & Yes & TIN & 50 & -2 & 87 & Yes
Sb & Natural Antimony & 296 & ENDF/B–VIIR0 & Yes & ANTIMONY & 51 & -2 & 296 & No
Sb & Natural Antimony & 87 & ENDF/B–VIIR0 & Yes & ANTIMONY & 51 & -2 & 87 & No
Te & Natural Tellurium & 296 & ENDF/B–VIIIR0 & Yes & ANTIMONY & 52 & -2 & 296 & No
I & Iodine 127 & 296 & ENDF/B–VIIR0 & Yes & IODINE & 53 & 127 & 296 & Yes
\(^{127}\)I & Iodine 127 & 87 & ENDF/B–VIIR0 & Yes & IODINE & 53 & 127 & 87 & Yes
\(^{129}\)I & Iodine 129\(^{\,(2)}\) & 296 & ENDF/B–VIIR0 & Yes & 129-I & 53 & 129 & 296 & No
\(^{129}\)I & Iodine 129\(^{\,(2)}\) & 87 & ENDF/B–VIIR0 & Yes & 129-I & 53 & 129 & 87 & No
Xe & Natural Xenon\(^{\,(2)}\) & 296 & ENDF/B–VIIR0 & Yes & XENON & 54 & -2 & 296 & No
Xe & Natural Xenon\(^{\,(2)}\) & 87 & ENDF/B–VIIR0 & Yes & XENON & 54 & -2 & 87 & No
\(^{124}\)Xe & Xenon 124 & 296 & ENDF/B–VIIR0 & Yes & 124-XE & 54 & 124 & 296 & No
\(^{124}\)Xe & Xenon 124 & 87 & ENDF/B–VIIR0 & Yes & 124-XE & 54 & 124 & 87 & No
\(^{126}\)Xe & Xenon 126 & 296 & ENDF/B–VIIR0 & Yes & 126-XE & 54 & 126 & 296 & No
\(^{126}\)Xe & Xenon 126 & 87 & ENDF/B–VIIR0 & Yes & 126-XE & 54 & 126 & 87 & No
\(^{128}\)Xe & Xenon 128 & 296 & ENDF/B–VIIR0 & Yes & 128-XE & 54 & 128 & 296 & No
\(^{128}\)Xe & Xenon 128 & 87 & ENDF/B–VIIR0 & Yes & 128-XE & 54 & 128 & 87 & No
\(^{129}\)Xe & Xenon 129 & 296 & ENDF/B–VIIR0 & Yes & 129-XE & 54 & 129 & 296 & No
\(^{129}\)Xe & Xenon 129 & 87 & ENDF/B–VIIR0 & Yes & 129-XE & 54 & 129 & 87 & No
\(^{130}\)Xe & Xenon 130 & 296 & ENDF/B–VIIR0 & Yes & 130-XE & 54 & 130 & 296 & No
\(^{130}\)Xe & Xenon 130 & 87 & ENDF/B–VIIR0 & Yes & 130-XE & 54 & 130 & 87 & No
\(^{131}\)Xe & Xenon 131 & 296 & ENDF/B–VIIR0 & Yes & 131-XE & 54 & 131 & 296 & Yes
\(^{131}\)Xe & Xenon 131 & 87 & ENDF/B–VIIR0 & Yes & 131-XE & 54 & 131 & 87 & Yes
\(^{132}\)Xe & Xenon 132 & 296 & ENDF/B–VIIR0 & Yes & 132-XE & 54 & 132 & 296 & No
\(^{132}\)Xe & Xenon 132 & 87 & ENDF/B–VIIR0 & Yes & 132-XE & 54 & 132 & 87 & No
\(^{134}\)Xe & Xenon 134 & 296 & ENDF/B–VIIR0 & Yes & 134-XE & 54 & 134 & 296 & No
\(^{134}\)Xe & Xenon 134 & 87 & ENDF/B–VIIR0 & Yes & 134-XE & 54 & 134 & 87 & No
\(^{135}\)Xe & Xenon 135 & 296 & ENDF/B–VIIR0 & Yes & 135-XE & 54 & 135 & 296 & No
\(^{135}\)Xe & Xenon 135 & 87 & ENDF/B–VIIR0 & Yes & 135-XE & 54 & 135 & 87 & No
\(^{136}\)Xe & Xenon 136 & 296 & ENDF/B–VIIR0 & Yes & 136-XE & 54 & 136 & 296 & No
\(^{136}\)Xe & Xenon 136 & 87 & ENDF/B–VIIR0 & Yes & 136-XE & 54 & 136 & 87 & No
\(^{133}\)Cs & Cesium 133 & 296 & ENDF/B–VIIIR0 & Yes & CESIUM & 55 & 133 & 296 & Yes
\(^{133}\)Cs & Cesium 133 & 87 & ENDF/B–VIIIR0 & Yes & CESIUM & 55 & 133 & 87 & Yes
\(^{135}\)Cs & Cesium 135\(^{\,(2)}\) & 296 & ENDF/B–VIIR0 & Yes & 135-CS & 55 & 135 & 296 & No
\(^{135}\)Cs & Cesium 135\(^{\,(2)}\) & 87 & ENDF/B–VIIR0 & Yes & 135-CS & 55 & 135 & 87 & No
\(^{137}\)Cs & Cesium 137\(^{\,(2)}\) & 296 & ENDF/B–VIIR0 & Yes & 137-CS & 55 & 137 & 296 & No
\(^{137}\)Cs & Cesium 137\(^{\,(2)}\) & 87 & ENDF/B–VIIR0 & Yes & 137-CS & 55 & 137 & 87 & No
Ba & Natural Barium\(^{\,(2)}\) & 296 & TENDL–12/14 & Yes & BARIUM & 56 & -2 & 296 & Yes
Ba & Natural Barium\(^{\,(2)}\) & 87 & TENDL–12/14 & Yes & BARIUM & 56 & -2 & 87 & Yes
La & Natural Lanthanum & 296 & JEFF–3.2 & Yes & LANTHANU & 57 & -2 & 296 & Yes
La & Natural Lanthanum & 87 & JEFF–3.2 & Yes & LANTHANU & 57 & -2 & 87 & Yes
Ce & Natural Cerium\(^{\,(2)}\) & 296 & ENDF/B–VIIIR0 & Yes & CERIUM & 58 & -2 & 296 & No
Ce & Natural Cerium\(^{\,(2)}\) & 87 & ENDF/B–VIIIR0 & Yes & CERIUM & 58 & -2 & 87 & No
Nd & Natural Neodymium & 296 & ENDF/B–VIIR0 & Yes & NEODYMIU & 60 & -2 & 296 & Yes
Nd & Natural Neodymium & 87 & ENDF/B–VIIR0 & Yes & NEODYMIU & 60 & -2 & 87 & Yes
Sm & Natural Samarium\(^{\,(2)}\) & 296 & ENDF/B–VIIR0 & Yes & SAMARIUM & 62 & -2 & 296 & Yes
Sm & Natural Samarium\(^{\,(2)}\) & 87 & ENDF/B–VIIR0 & Yes & SAMARIUM & 62 & -2 & 87 & Yes
Eu & Natural Europium\(^{\,(3)}\) & 296 & ENDF/B–VIIIR0 & Yes & EUROPIUM & 63 & -2 & 296 & Yes
Eu & Natural Europium\(^{\,(3)}\) & 87 & ENDF/B–VIIIR0 & Yes & EUROPIUM & 63 & -2 & 87 & Yes
Gd & Natural Gadolinium & 296 & ENDF/B–VIIR0 & Yes & GADOLINI & 64 & -2 & 296 & Yes
Gd & Natural Gadolinium & 87 & ENDF/B–VIIR0 & Yes & GADOLINI & 64 & -2 & 87 & Yes
\(^{159}\)Tb & Terbium 159 & 296 & ENDF/B–VIIR0 & Yes & TERBIUM & 65 & 159 & 296 & No
\(^{159}\)Tb & Terbium 159 & 87 & ENDF/B–VIIR0 & Yes & TERBIUM & 65 & 159 & 87 & No
Dy & Natural Dysprosium\(^{\,(2)}\) & 296 & ENDF/B–VIIIR0 & Yes & DYSPROSI & 66 & -2 & 296 & Yes
\(^{165}\)Ho & Holmium 165 & 296 & ENDF/B–VIIIR0 & Yes & HOLMIUM & 67 & 165 & 296 & Yes
\(^{165}\)Ho & Holmium 165 & 87 & ENDF/B–VIIIR0 & Yes & HOLMIUM & 67 & 165 & 87 & Yes
Lu & Natural Lutetium\(^{\,(2)}\) & 296 & TENDL–19 & Yes & LUTETIUM & 71 & -2 & 296 & Yes
Lu & Natural Lutetium\(^{\,(2)}\) & 87 & TENDL–19 & Yes & LUTETIUM & 71 & -2 & 87 & Yes
Hf & Natural Hafnium & 296 & ENDF/B-VIIIR0 & Yes & HAFNIUM & 72 & -2 & 296 & Yes
Hf & Natural Hafnium & 87 & ENDF/B-VIIIR0 & Yes & HAFNIUM & 72 & -2 & 87 & Yes
\(^{181}\)Ta & Tantalum 181 & 296 & ENDF/B–VIIIR0 & Yes & TANTALUM & 73 & 181 & 296 & Yes
\(^{181}\)Ta & Tantalum 181 & 87 & ENDF/B–VIIIR0 & Yes & TANTALUM & 73 & 181 & 87 & Yes
\(^{181}\)Ta & Tantalum 181 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & TANTALUM & 73 & 1181 & 296 & Yes
\(^{181}\)Ta & Tantalum 181 SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & TANTALUM & 73 & 1181 & 87 & Yes
W & Natural Tungsten\(^{\,(2)}\) & 296 & ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -2 & 296 & Yes
W & Natural Tungsten\(^{\,(2)}\) & 87 & ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -2 & 87 & Yes
W & Natural Tungsten\(^{\,(2)}\) & 4 & ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -2 & 4 & Yes
W & Natural Tungsten\(^{\,(2)}\) & 430 & ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -2 & 430 & Yes
W & Natural Tungsten SelfShielded\(^{\,(2)}\)&296& ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -4 & 296 & Yes
W & Natural Tungsten SelfShielded\(^{\,(2)}\)& 87& ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -4 & 87 & Yes
W & Natural Tungsten SelfShielded\(^{\,(2)}\)& 4& ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -4 & 4 & Yes
W & Natural Tungsten SelfShielded\(^{\,(2)}\)&430& ENDF/B–VIIIR0 & Yes & TUNGSTEN & 74 & -4 & 430 & Yes
Re & Natural Rhenium & 296 & ENDF/B-VIIIR0 & Yes & RHENIUM & 75 & -2 & 296 & Yes
Re & Natural Rhenium & 87 & ENDF/B-VIIIR0 & Yes & RHENIUM & 75 & -2 & 87 & Yes
Os & Natural Osmium\(^{\,(2)}\) & 296 & ENDF/B-VIIIR0 & Yes & OSMIUM & 76 & -2 & 296 & Yes
Os & Natural Osmium\(^{\,(2)}\) & 87 & ENDF/B-VIIIR0 & Yes & OSMIUM & 76 & -2 & 87 & Yes
Ir & Natural Iridium\(^{\,(2)}\) & 296 & ENDF/B-VIIR0 & Yes & IRIDIUM & 77 & -2 & 296 & Yes
Ir & Natural Iridium\(^{\,(2)}\) & 87 & ENDF/B-VIIR0 & Yes & IRIDIUM & 77 & -2 & 87 & Yes
Pt & Natural Platinum & 296 & JEFF–3.2 & No & PLATINUM & 78 & -2 & 296 & Yes
Pt & Natural Platinum & 87 & JEFF–3.2 & No & PLATINUM & 78 & -2 & 87 & Yes
\(^{197}\)Au & Gold 197 & 296 & ENDF/B–VIIIR0 & Yes & GOLD & 79 & 197 & 296 & Yes
\(^{197}\)Au & Gold 197 & 87 & ENDF/B–VIIIR0 & Yes & GOLD & 79 & 197 & 87 & Yes  \(^{197}\)Au & Gold 197 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & GOLD & 79 & 1197 & 296 & Yes
\(^{197}\)Au & Gold 197 SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & GOLD & 79 & 1197 & 87 & Yes
\(^{197}\)Au & Gold 197 0.1mm SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & GOLD & 79 & 2197 & 296 & Yes
Hg & Natural Mercury\(^{\,(2)}\) & 296 & ENDF/B–VIIR0 & Yes & MERCURY & 80 & -2 & 296 & Yes  Hg & Natural Mercury\(^{\,(2)}\) & 87 & ENDF/B–VIIR0 & Yes & MERCURY & 80 & -2 & 87 & Yes  Tl & Natural Thallium & 296 & ENDF/B–VIIIR0 & Yes & THALLIUM & 81 & -2 & 296 & Yes  Tl & Natural Thallium & 87 & ENDF/B–VIIIR0 & Yes & THALLIUM & 81 & -2 & 87 & Yes  Pb & Natural Lead & 296 & ENDF/B–VIIIR0 & Yes & LEAD & 82 & -2 & 296 & Yes
Pb & Natural Lead & 87 & ENDF/B–VIIIR0 & Yes & LEAD & 82 & -2 & 87 & Yes
Pb & Natural Lead SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & LEAD & 82 & -4 & 296 & Yes  Pb & Natural Lead SelfShielded & 87 & ENDF/B–VIIIR0 & Yes & LEAD & 82 & -4 & 87 & Yes  \(^{208}\)Pb & Lead 208 & 296 & ENDF/B–VIIIR0 & Yes & 208-PB & 82 & 208 & 296 & Yes  \(^{208}\)Pb & Lead 208 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & 208-PB & 82 & 1208 & 296 & Yes  \(^{209}\)Bi & Bismuth 209 & 296 & ENDF/B–VIIR1 & Yes & BISMUTH & 83 & 209 & 296 & Yes
\(^{209}\)Bi & Bismuth 209 & 87 & ENDF/B–VIIR1 & Yes & BISMUTH & 83 & 209 & 87 & Yes  \(^{209}\)Bi & Bismuth 209 SelfShielded & 296 & ENDF/B–VIIR1 & Yes & BISMUTH & 83 & 1209 & 296 & Yes
\(^{209}\)Bi & Bismuth 209 SelfShielded & 87 & ENDF/B–VIIR1 & Yes & BISMUTH & 83 & 1209 & 87 & Yes
\(^{226}\)Ra & Radium 226 & 296 & TENDL–19 & Yes & 226-RA & 88 & 226 & 296 & Yes
\(^{226}\)Ra & Radium 226 & 87 & TENDL–19 & Yes & 226-RA & 88 & 226 & 87 & Yes
\(^{227}\)Ac & Actinium 227 & 296 & TENDL–19 & Yes & 227-AC & 89 & 227 & 296 & Yes
\(^{227}\)Ac & Actinium 227 & 87 & TENDL–19 & Yes & 227-AC & 89 & 227 & 87 & Yes
\(^{230}\)Th & Thorium 230 & 296 & ENDF/B–VIIIR0 & Yes & 230-TH & 90 & 230 & 296 & Yes
\(^{230}\)Th & Thorium 230 & 87 & ENDF/B–VIIIR0 & Yes & 230-TH & 90 & 230 & 87 & Yes
\(^{232}\)Th & Thorium 232 & 296 & ENDF/B–VIIIR0 & Yes & 232-TH & 90 & 232 & 296 & Yes
\(^{232}\)Th & Thorium 232 & 87 & ENDF/B–VIIIR0 & Yes & 232-TH & 90 & 232 & 87 & Yes
\(^{232}\)Th & Thorium 232 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & 232-TH & 90 & 1232 & 296 & Yes
\(^{231}\)Pa & Protactinium 231 & 296 & ENDF/B–VIIIR0 & Yes & 231-PA & 91 & 231 & 296 & Yes
\(^{231}\)Pa & Protactinium 231 & 87 & ENDF/B–VIIIR0 & Yes & 231-PA & 91 & 231 & 87 & Yes
\(^{233}\)Pa & Protactinium 233 & 296 & ENDF/B–VIIIR0 & Yes & 233-PA & 91 & 233 & 296 & Yes
\(^{233}\)Pa & Protactinium 233 & 87 & ENDF/B–VIIIR0 & Yes & 233-PA & 91 & 233 & 87 & Yes
\(^{233}\)U & Uranium 233 & 296 & ENDF/B–VIIIR0 & Yes & 233-U & 92 & 233 & 296 & Yes
\(^{233}\)U & Uranium 233 & 87 & ENDF/B–VIIIR0 & Yes & 233-U & 92 & 233 & 87 & Yes
\(^{234}\)U & Uranium 234 & 296 & ENDF/B–VIIIR0 & Yes & 234-U & 92 & 234 & 296 & Yes
\(^{234}\)U & Uranium 234 & 87 & ENDF/B–VIIIR0 & Yes & 234-U & 92 & 234 & 87 & Yes
\(^{235}\)U & Uranium 235 & 296 & ENDF/B–VIIIR0 & Yes & 235-U & 92 & 235 & 296 & Yes  \(^{235}\)U & Uranium 235 & 87 & ENDF/B–VIIIR0 & Yes & 235-U & 92 & 235 & 87 & Yes  \(^{238}\)U & Uranium 238 & 296 & ENDF/B–VIIIR0 & Yes & 238-U & 92 & 238 & 296 & Yes  \(^{238}\)U & Uranium 238 & 87 & ENDF/B–VIIIR0 & Yes & 238-U & 92 & 238 & 87 & Yes  \(^{237}\)Np & Neptunium 237 & 296 & ENDF/B–VIIIR0 & Yes & 237-NP & 93 & 237 & 296 & Yes
\(^{237}\)Np & Neptunium 237 & 87 & ENDF/B–VIIIR0 & Yes & 237-NP & 93 & 237 & 87 & Yes
\(^{239}\)Np & Neptunium 239 & 296 & TENDL–19 & Yes & 239-NP & 93 & 239 & 296 & Yes
\(^{239}\)Np & Neptunium 239 & 87 & TENDL–19 & Yes & 239-NP & 93 & 239 & 87 & Yes
\(^{239}\)Pu & Plutonium 239 & 296 & ENDF/B–VIIIR0 & Yes & 239-PU & 94 & 239 & 296 & Yes
\(^{239}\)Pu & Plutonium 239 & 87 & ENDF/B–VIIIR0 & Yes & 239-PU & 94 & 239 & 87 & Yes
\(^{239}\)Pu & Plutonium 239 SelfShielded & 296 & ENDF/B–VIIIR0 & Yes & 239-PU & 94 & 1239 & 296 & Yes
\(^{241}\)Am & Americium 241 & 296 & ENDF/B–VIIR0 & Yes & 241-AM & 95 & 241 & 296 & Yes
\(^{241}\)Am & Americium 241 & 87 & ENDF/B–VIIR0 & Yes & 241-AM & 95 & 241 & 87 & Yes
\(^{243}\)Am & Americium 243 & 296 & ENDF/B–VIIR0 & Yes & 243-AM & 95 & 243 & 296 & Yes
\(^{243}\)Am & Americium 243 & 87 & ENDF/B–VIIR0 & Yes & 243-AM & 95 & 243 & 87 & Yes

Kerma factor not very satisfactory, particularly for \(^{36}\)S
Bad kerma factor
Actually \(^{151}\)Eu from TENDL–19, \(^{153}\)Eu from ENDF/B–VIIIR0

Full pointwise transport¶

Starting with FLUKA2021.2 neutron transport can be done also using continuous (pointwise) cross sections. For \(^1\)H, \(^2\)H, \(^3\)He, \(^4\)He, and \(^{12}\)C fully correlated pointwise cross sections are built-in inside the code, and are automatically processed at the temperature(s) required by the problem. For many other isotopes fully correlated pointwise cross sections are available in external files (directory pwxs) generated out of evaluated data files. In all cases, all secondaries, including charged particles and recoils are explicitly generated.

Binding effect (eg H in water, H in polyethylene, C in graphite…) are not yet implemented, all isotopes are treated as free gas in the thermal region. However by default, for those isotopes for which bound cross sections exist and are requested in the multi-group library, the pointwise treatment will be stopped at 3.059023 eV and the bound groupwise treatment used below that energy. This default behaviour can be overriden setting WHAT(6) in LOW–NEUT, however this is strongly discouraged.

The easiest way to activate pointwise cross sections is to issue a LOW–PWXS card like:

All isotopes for all materials at 296 K, leaving Fluka to decide which
evaluations to pick up for each of them:
*...+....1....+....2....+....3....+....4....+....5....+....6....+....7....+...
LOW-PWXS   1.0                                 3.0  @LASTMAT

The code will automatically split each element into the constituent isotopes and pick up the corresponding pointwise cross section for each isotope. Please look into the output file if you want to know the exact details about how the association isotope to pointwise cross section set is performed.

The CPU penalty for using pointwise cross sections can be significant. The number of energy-cross section pairs can be very large (eg 96033 points for 56Fe total cross section, ENDF/B-VIIIR0, at 296 K), and the generation of secondaries much more complex with respect to multi-group cross sections. On top of these considerations, the transport of the generated charged products can in itself take up a considerable computer time.

Resonances and self-shielding with pointwise cross sections¶

Resolved resonances are obviously fully described in the pointwise cross sections, properly broadened at the given temperature. In the resolved resonance energy range self-shielding is automatically accounted for.

For materials with no unresolved resonance regions, no further consideration is required.

When unresolved resonance regions (URR’s) are present, even pointwise cross sections have a problem with self-shielding. In order to solve this issue, offline generated statistical distributions of cross sections are sampled from at run-time. This procedure is implemented in the FLUKA pointwise approach, and therefore partial or full self-shielding is automatically assured in all conditions and energy ranges.

Secondary particle emission with pointwise cross sections¶

All secondary particles, neutrons, charged particles, recoils, are produced in a completely correlated manner, that is energy and momentum are conserved exactly at each neutron interactions. The user should be aware that the secondary particle distributions available in the evaluated data files are inclusive, that is they do not provide the correlations among the various products. Hence considerable work is required to develop interaction models which reproduce as much as possible the inclusive distributions provided in the evaluated data files, while at the same time generating fully correlated events.

An exact reproduction of the inclusive distribution is sometimes impossible to achieve, priority is always given to match as much as possible the one of the emitted neutrons. Often evaluated data contain inclusive distributions which are plainly inconsistent with energy conservation for the given reaction channel. In those cases corrections with respect to the tabulated inclusive distributions are applied in order to bring them in compliance with basic conservation laws.

There are several degrees of arbitrariness in these procedures, particularly for complex reactions with many emitted secondaries. Physics considerations are applied in order to solve hopefully for the best these issues. However the user should not expect to obtain results which are exactly reproducing the inclusive distributions contained in the original evaluated data file.

Photon emission with pointwise cross sections¶

For reaction involving particle emissions, often the final, ground state or excited, level ofthe residual nucleus is not provided in the evaluated data files. The FLUKA implementation tries to guess as best as possible the final excitation on the basis of the inclusive spectra of the emitted particles and physics consideration. The following de-excitation is performed using the standard FLUKA de-excitation models, which heavily rely on experimental data when within the range of known levels.

For (n,\(\gamma\)) reactions in the thermal region, the capture photons emission schemes are as much as possible based on experimental data of primary de-excitation from the capture level as available in the ENSDF database. For many light and medium isotopes the available data are more or less complete. For medium to heavy nuclei, the available data, when present, often cover only a fraction of the possible schemes. The missing informations are generated as usual by the FLUKA de-excitation models. Therefore the agreement with experimental secondary lines can be very good when primary ones are almost completely known, questionable otherwise. It should be noted that even evaluated data files often contain model calculated capture gamma spectra, in some cases not even in agreement with experimentally known primary lines.

For capture reactions in the resonance region, the same de-excitation schemes of the thermal range are applied. This is obviously not correct since the spin and parity of the given resonance could be different from those of thermal capture, however the experimental data about gamma spectra in the resonance region are very scarce.

As a consequence of all the above consideration, production of a specific isomer can be very accurate in some cases, eg for (n,n’) specifically ending up on that level, or much less accurate in others. If accurate predictions os isomers are of importance, it is better to rely on the group-wise cross sections which contain their (uncorrelated) production branchings as derived from available evaluated activation files.

Fission with pointwise cross sections¶

Prompt fission is described in a fully correlated manner by means of a simple fission model. As such, the exact reproduction of the inclusive distributions of fission fragments, fission neutron multiplicities and energies are not assured. On the other hand, fully correlated events not very far from reality can be simulated allowing to study for example the single event response of a detector.

The fission model parameters have been tuned so that \(<\nu_{prompt}>\) for the most important isotopes are well reproduced, particularly for those isotopes with significant fission cross sections in the thermal region.

Delayed neutrons are not yet generated, they will come in a future release.

List of isotopes for which pointwise cross sections are available¶

At present pointwise cross sections are available for the following isotopes, besides \(^1\)H, \(^2\)H, \(^3\)He, \(^4\)He, and \(^{12}\)C:

Isotope	Temperature	Source

\(^{6}\)Li	87 K	ENDF/B–VIIIR0
\(^{6}\)Li	296 K	ENDF/B–VIIIR0
\(^{7}\)Li	87 K	ENDF/B–VIIIR0
\(^{7}\)Li	296 K	ENDF/B–VIIIR0
\(^{9}\)Be	87 K	ENDF/B–VIIIR0
\(^{9}\)Be	296 K	ENDF/B–VIIIR0
\(^{10}\)B	87 K	ENDF/B–VIIIR0
\(^{10}\)B	296 K	ENDF/B–VIIIR0
\(^{11}\)B	87 K	ENDF/B–VIIIR0
\(^{11}\)B	296 K	ENDF/B–VIIIR0
\(^{13}\)C	4 K	ENDF/B–VIIIR0
\(^{13}\)C	87 K	ENDF/B–VIIIR0
\(^{13}\)C	296 K	ENDF/B–VIIIR0
\(^{13}\)C	430 K	ENDF/B–VIIIR0
\(^{13}\)C	686 K	ENDF/B–VIIIR0
\(^{14}\)N	87 K	ENDF/B–VIIIR0
\(^{14}\)N	296 K	ENDF/B–VIIIR0
\(^{15}\)N	87 K	ENDF/B–VIIIR0
\(^{15}\)N	296 K	ENDF/B–VIIIR0
\(^{16}\)O	4 K	ENDF/B–VIIIR0
\(^{16}\)O	87 K	ENDF/B–VIIIR0
\(^{16}\)O	296 K	ENDF/B–VIIIR0
\(^{16}\)O	430 K	ENDF/B–VIIIR0
\(^{16}\)O	686 K	ENDF/B–VIIIR0
\(^{17}\)O	4 K	ENDF/B–VIIIR0
\(^{17}\)O	87 K	ENDF/B–VIIIR0
\(^{17}\)O	296 K	ENDF/B–VIIIR0
\(^{17}\)O	430 K	ENDF/B–VIIIR0
\(^{17}\)O	686 K	ENDF/B–VIIIR0
\(^{18}\)O	4 K	ENDF/B–VIIIR0
\(^{18}\)O	87 K	ENDF/B–VIIIR0
\(^{18}\)O	296 K	ENDF/B–VIIIR0
\(^{18}\)O	430 K	ENDF/B–VIIIR0
\(^{18}\)O	686 K	ENDF/B–VIIIR0
\(^{19}\)F	87 K	ENDF/B–VIIIR0
\(^{19}\)F	296 K	ENDF/B–VIIIR0
\(^{20}\)Ne	87 K	TENDL–19
\(^{20}\)Ne	296 K	TENDL–19
\(^{21}\)Ne	87 K	TENDL–19
\(^{21}\)Ne	296 K	TENDL–19
\(^{22}\)Ne	87 K	TENDL–19
\(^{22}\)Ne	296 K	TENDL–19
\(^{23}\)Na	87 K	ENDF/B–VIIIR0
\(^{23}\)Na	296 K	ENDF/B–VIIIR0
\(^{24}\)Mg	87 K	ENDF/B–VIIIR0
\(^{24}\)Mg	296 K	ENDF/B–VIIIR0
\(^{25}\)Mg	87 K	ENDF/B–VIIIR0
\(^{25}\)Mg	296 K	ENDF/B–VIIIR0
\(^{26}\)Mg	87 K	ENDF/B–VIIIR0
\(^{26}\)Mg	296 K	ENDF/B–VIIIR0
\(^{27}\)Al	4 K	ENDF/B–VIIIR0
\(^{27}\)Al	87 K	ENDF/B–VIIIR0
\(^{27}\)Al	296 K	ENDF/B–VIIIR0
\(^{27}\)Al	430 K	ENDF/B–VIIIR0
\(^{27}\)Al	686 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{28}\)Si	4 K	ENDF/B–VIIIR0
\(^{28}\)Si	87 K	ENDF/B–VIIIR0
\(^{28}\)Si	296 K	ENDF/B–VIIIR0
\(^{28}\)Si	430 K	ENDF/B–VIIIR0
\(^{28}\)Si	686 K	ENDF/B–VIIIR0
\(^{29}\)Si	4 K	ENDF/B–VIIIR0
\(^{29}\)Si	87 K	ENDF/B–VIIIR0
\(^{29}\)Si	296 K	ENDF/B–VIIIR0
\(^{29}\)Si	430 K	ENDF/B–VIIIR0
\(^{29}\)Si	686 K	ENDF/B–VIIIR0
\(^{30}\)Si	4 K	ENDF/B–VIIIR0
\(^{30}\)Si	87 K	ENDF/B–VIIIR0
\(^{30}\)Si	296 K	ENDF/B–VIIIR0
\(^{30}\)Si	430 K	ENDF/B–VIIIR0
\(^{30}\)Si	686 K	ENDF/B–VIIIR0
\(^{31}\)P	87 K	ENDF/B–VIIIR0
\(^{31}\)P	296 K	ENDF/B–VIIIR0
\(^{32}\)S	87 K	ENDF/B–VIIIR0
\(^{32}\)S	296 K	ENDF/B–VIIIR0
\(^{33}\)S	87 K	ENDF/B–VIIIR0
\(^{33}\)S	296 K	ENDF/B–VIIIR0
\(^{34}\)S	87 K	ENDF/B–VIIIR0
\(^{34}\)S	296 K	ENDF/B–VIIIR0
\(^{36}\)S	87 K	ENDF/B–VIIIR0
\(^{36}\)S	296 K	ENDF/B–VIIIR0
\(^{35}\)Cl	87 K	ENDF/B–VIIIR0
\(^{35}\)Cl	296 K	ENDF/B–VIIIR0
\(^{37}\)Cl	87 K	ENDF/B–VIIIR0
\(^{37}\)Cl	296 K	ENDF/B–VIIIR0
\(^{36}\)Ar	87 K	ENDF/B–VIIIR0
\(^{36}\)Ar	296 K	ENDF/B–VIIIR0
\(^{38}\)Ar	87 K	TENDL–19
\(^{38}\)Ar	296 K	TENDL–19
\(^{40}\)Ar	87 K	ENDF/B–VIIIR0
\(^{40}\)Ar	296 K	ENDF/B–VIIIR0
\(^{39}\)K	87 K	ENDF/B–VIIIR0
\(^{39}\)K	296 K	ENDF/B–VIIIR0
\(^{40}\)K	87 K	ENDF/B–VIIIR0
\(^{40}\)K	296 K	ENDF/B–VIIIR0
\(^{41}\)K	87 K	ENDF/B–VIIIR0
\(^{41}\)K	296 K	ENDF/B–VIIIR0
\(^{40}\)Ca	87 K	ENDF/B–VIIIR0
\(^{40}\)Ca	296 K	ENDF/B–VIIIR0
\(^{42}\)Ca	87 K	ENDF/B–VIIIR0
\(^{42}\)Ca	296 K	ENDF/B–VIIIR0
\(^{43}\)Ca	87 K	ENDF/B–VIIIR0
\(^{43}\)Ca	296 K	ENDF/B–VIIIR0
\(^{44}\)Ca	87 K	ENDF/B–VIIIR0
\(^{44}\)Ca	296 K	ENDF/B–VIIIR0
\(^{46}\)Ca	87 K	ENDF/B–VIIIR0
\(^{46}\)Ca	296 K	ENDF/B–VIIIR0
\(^{48}\)Ca	87 K	ENDF/B–VIIIR0
\(^{48}\)Ca	296 K	ENDF/B–VIIIR0
\(^{45}\)Sc	87 K	ENDF/B–VIIIR0
\(^{45}\)Sc	296 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{46}\)Ti	4 K	ENDF/B–VIIIR0
\(^{46}\)Ti	87 K	ENDF/B–VIIIR0
\(^{46}\)Ti	296 K	ENDF/B–VIIIR0
\(^{46}\)Ti	430 K	ENDF/B–VIIIR0
\(^{46}\)Ti	686 K	ENDF/B–VIIIR0
\(^{47}\)Ti	4 K	ENDF/B–VIIIR0
\(^{47}\)Ti	87 K	ENDF/B–VIIIR0
\(^{47}\)Ti	296 K	ENDF/B–VIIIR0
\(^{47}\)Ti	430 K	ENDF/B–VIIIR0
\(^{47}\)Ti	686 K	ENDF/B–VIIIR0
\(^{48}\)Ti	4 K	ENDF/B–VIIIR0
\(^{48}\)Ti	87 K	ENDF/B–VIIIR0
\(^{48}\)Ti	296 K	ENDF/B–VIIIR0
\(^{48}\)Ti	430 K	ENDF/B–VIIIR0
\(^{48}\)Ti	686 K	ENDF/B–VIIIR0
\(^{49}\)Ti	4 K	ENDF/B–VIIIR0
\(^{49}\)Ti	87 K	ENDF/B–VIIIR0
\(^{49}\)Ti	296 K	ENDF/B–VIIIR0
\(^{49}\)Ti	430 K	ENDF/B–VIIIR0
\(^{49}\)Ti	686 K	ENDF/B–VIIIR0
\(^{50}\)Ti	4 K	ENDF/B–VIIIR0
\(^{50}\)Ti	87 K	ENDF/B–VIIIR0
\(^{50}\)Ti	296 K	ENDF/B–VIIIR0
\(^{50}\)Ti	430 K	ENDF/B–VIIIR0
\(^{50}\)Ti	686 K	ENDF/B–VIIIR0
\(^{50}\)V	87 K	ENDF/B–VIIIR0
\(^{50}\)V	296 K	ENDF/B–VIIIR0
\(^{51}\)V	87 K	ENDF/B–VIIIR0
\(^{51}\)V	296 K	ENDF/B–VIIIR0
\(^{50}\)Cr	4 K	ENDF/B–VIIIR0
\(^{50}\)Cr	87 K	ENDF/B–VIIIR0
\(^{50}\)Cr	296 K	ENDF/B–VIIIR0
\(^{50}\)Cr	430 K	ENDF/B–VIIIR0
\(^{50}\)Cr	686 K	ENDF/B–VIIIR0
\(^{52}\)Cr	4 K	ENDF/B–VIIIR0
\(^{52}\)Cr	87 K	ENDF/B–VIIIR0
\(^{52}\)Cr	296 K	ENDF/B–VIIIR0
\(^{52}\)Cr	430 K	ENDF/B–VIIIR0
\(^{52}\)Cr	686 K	ENDF/B–VIIIR0
\(^{53}\)Cr	4 K	ENDF/B–VIIIR0
\(^{53}\)Cr	87 K	ENDF/B–VIIIR0
\(^{53}\)Cr	296 K	ENDF/B–VIIIR0
\(^{53}\)Cr	430 K	ENDF/B–VIIIR0
\(^{53}\)Cr	686 K	ENDF/B–VIIIR0
\(^{54}\)Cr	4 K	ENDF/B–VIIIR0
\(^{54}\)Cr	87 K	ENDF/B–VIIIR0
\(^{54}\)Cr	296 K	ENDF/B–VIIIR0
\(^{54}\)Cr	430 K	ENDF/B–VIIIR0
\(^{54}\)Cr	686 K	ENDF/B–VIIIR0
\(^{55}\)Mn	4 K	ENDF/B–VIIR0
\(^{55}\)Mn	87 K	ENDF/B–VIIR0
\(^{55}\)Mn	296 K	ENDF/B–VIIR0
\(^{55}\)Mn	430 K	ENDF/B–VIIR0
\(^{55}\)Mn	686 K	ENDF/B–VIIR0
\(^{55}\)Mn	4 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{55}\)Mn	87 K	ENDF/B–VIIIR0
\(^{55}\)Mn	296 K	ENDF/B–VIIIR0
\(^{55}\)Mn	430 K	ENDF/B–VIIIR0
\(^{55}\)Mn	686 K	ENDF/B–VIIIR0
\(^{54}\)Fe	4 K	ENDF/B–VIIR1
\(^{54}\)Fe	87 K	ENDF/B–VIIR1
\(^{54}\)Fe	296 K	ENDF/B–VIIR1
\(^{54}\)Fe	430 K	ENDF/B–VIIR1
\(^{54}\)Fe	686 K	ENDF/B–VIIR1
\(^{54}\)Fe	4 K	ENDF/B–VIIIR0
\(^{54}\)Fe	87 K	ENDF/B–VIIIR0
\(^{54}\)Fe	296 K	ENDF/B–VIIIR0
\(^{54}\)Fe	430 K	ENDF/B–VIIIR0
\(^{54}\)Fe	686 K	ENDF/B–VIIIR0
\(^{56}\)Fe	4 K	ENDF/B–VIIR1
\(^{56}\)Fe	87 K	ENDF/B–VIIR1
\(^{56}\)Fe	296 K	ENDF/B–VIIR1
\(^{56}\)Fe	430 K	ENDF/B–VIIR1
\(^{56}\)Fe	686 K	ENDF/B–VIIR1
\(^{56}\)Fe	4 K	ENDF/B–VIIIR0
\(^{56}\)Fe	87 K	ENDF/B–VIIIR0
\(^{56}\)Fe	296 K	ENDF/B–VIIIR0
\(^{56}\)Fe	430 K	ENDF/B–VIIIR0
\(^{56}\)Fe	686 K	ENDF/B–VIIIR0
\(^{57}\)Fe	4 K	ENDF/B–VIIR1
\(^{57}\)Fe	87 K	ENDF/B–VIIR1
\(^{57}\)Fe	296 K	ENDF/B–VIIR1
\(^{57}\)Fe	430 K	ENDF/B–VIIR1
\(^{57}\)Fe	686 K	ENDF/B–VIIR1
\(^{57}\)Fe	4 K	ENDF/B–VIIIR0
\(^{57}\)Fe	87 K	ENDF/B–VIIIR0
\(^{57}\)Fe	296 K	ENDF/B–VIIIR0
\(^{57}\)Fe	430 K	ENDF/B–VIIIR0
\(^{57}\)Fe	686 K	ENDF/B–VIIIR0
\(^{58}\)Fe	4 K	ENDF/B–VIIR1
\(^{58}\)Fe	87 K	ENDF/B–VIIR1
\(^{58}\)Fe	296 K	ENDF/B–VIIR1
\(^{58}\)Fe	430 K	ENDF/B–VIIR1
\(^{58}\)Fe	686 K	ENDF/B–VIIR1
\(^{58}\)Fe	4 K	ENDF/B–VIIIR0
\(^{58}\)Fe	87 K	ENDF/B–VIIIR0
\(^{58}\)Fe	296 K	ENDF/B–VIIIR0
\(^{58}\)Fe	430 K	ENDF/B–VIIIR0
\(^{58}\)Fe	686 K	ENDF/B–VIIIR0
\(^{59}\)Co	4 K	ENDF/B–VIIIR0
\(^{59}\)Co	87 K	ENDF/B–VIIIR0
\(^{59}\)Co	296 K	ENDF/B–VIIIR0
\(^{59}\)Co	430 K	ENDF/B–VIIIR0
\(^{59}\)Co	686 K	ENDF/B–VIIIR0
\(^{58}\)Ni	4 K	ENDF/B–VIIIR0
\(^{58}\)Ni	87 K	ENDF/B–VIIIR0
\(^{58}\)Ni	296 K	ENDF/B–VIIIR0
\(^{58}\)Ni	430 K	ENDF/B–VIIIR0
\(^{58}\)Ni	686 K	ENDF/B–VIIIR0
\(^{60}\)Ni	4 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{60}\)Ni	87 K	ENDF/B–VIIIR0
\(^{60}\)Ni	296 K	ENDF/B–VIIIR0
\(^{60}\)Ni	430 K	ENDF/B–VIIIR0
\(^{60}\)Ni	686 K	ENDF/B–VIIIR0
\(^{61}\)Ni	4 K	ENDF/B–VIIIR0
\(^{61}\)Ni	87 K	ENDF/B–VIIIR0
\(^{61}\)Ni	296 K	ENDF/B–VIIIR0
\(^{61}\)Ni	430 K	ENDF/B–VIIIR0
\(^{61}\)Ni	686 K	ENDF/B–VIIIR0
\(^{62}\)Ni	4 K	ENDF/B–VIIIR0
\(^{62}\)Ni	87 K	ENDF/B–VIIIR0
\(^{62}\)Ni	296 K	ENDF/B–VIIIR0
\(^{62}\)Ni	430 K	ENDF/B–VIIIR0
\(^{62}\)Ni	686 K	ENDF/B–VIIIR0
\(^{64}\)Ni	4 K	ENDF/B–VIIIR0
\(^{64}\)Ni	87 K	ENDF/B–VIIIR0
\(^{64}\)Ni	296 K	ENDF/B–VIIIR0
\(^{64}\)Ni	430 K	ENDF/B–VIIIR0
\(^{64}\)Ni	686 K	ENDF/B–VIIIR0
\(^{63}\)Cu	4 K	ENDF/B–VIIIR0
\(^{63}\)Cu	87 K	ENDF/B–VIIIR0
\(^{63}\)Cu	296 K	ENDF/B–VIIIR0
\(^{63}\)Cu	430 K	ENDF/B–VIIIR0
\(^{63}\)Cu	686 K	ENDF/B–VIIIR0
\(^{65}\)Cu	4 K	ENDF/B–VIIIR0
\(^{65}\)Cu	87 K	ENDF/B–VIIIR0
\(^{65}\)Cu	296 K	ENDF/B–VIIIR0
\(^{65}\)Cu	430 K	ENDF/B–VIIIR0
\(^{65}\)Cu	686 K	ENDF/B–VIIIR0
\(^{64}\)Zn	4 K	ENDF/B–VIIIR0
\(^{64}\)Zn	87 K	ENDF/B–VIIIR0
\(^{64}\)Zn	296 K	ENDF/B–VIIIR0
\(^{64}\)Zn	430 K	ENDF/B–VIIIR0
\(^{64}\)Zn	686 K	ENDF/B–VIIIR0
\(^{66}\)Zn	4 K	ENDF/B–VIIIR0
\(^{66}\)Zn	87 K	ENDF/B–VIIIR0
\(^{66}\)Zn	296 K	ENDF/B–VIIIR0
\(^{66}\)Zn	430 K	ENDF/B–VIIIR0
\(^{66}\)Zn	686 K	ENDF/B–VIIIR0
\(^{67}\)Zn	4 K	ENDF/B–VIIIR0
\(^{67}\)Zn	87 K	ENDF/B–VIIIR0
\(^{67}\)Zn	296 K	ENDF/B–VIIIR0
\(^{67}\)Zn	430 K	ENDF/B–VIIIR0
\(^{67}\)Zn	686 K	ENDF/B–VIIIR0
\(^{68}\)Zn	4 K	ENDF/B–VIIIR0
\(^{68}\)Zn	87 K	ENDF/B–VIIIR0
\(^{68}\)Zn	296 K	ENDF/B–VIIIR0
\(^{68}\)Zn	430 K	ENDF/B–VIIIR0
\(^{68}\)Zn	686 K	ENDF/B–VIIIR0
\(^{70}\)Zn	4 K	ENDF/B–VIIIR0
\(^{70}\)Zn	87 K	ENDF/B–VIIIR0
\(^{70}\)Zn	296 K	ENDF/B–VIIIR0
\(^{70}\)Zn	430 K	ENDF/B–VIIIR0
\(^{70}\)Zn	686 K	ENDF/B–VIIIR0
\(^{69}\)Ga	87 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{69}\)Ga	296 K	ENDF/B–VIIIR0
\(^{71}\)Ga	87 K	ENDF/B–VIIIR0
\(^{71}\)Ga	296 K	ENDF/B–VIIIR0
\(^{70}\)Ge	87 K	ENDF/B–VIIIR0
\(^{70}\)Ge	296 K	ENDF/B–VIIIR0
\(^{72}\)Ge	87 K	ENDF/B–VIIIR0
\(^{72}\)Ge	296 K	ENDF/B–VIIIR0
\(^{73}\)Ge	87 K	ENDF/B–VIIIR0
\(^{73}\)Ge	296 K	ENDF/B–VIIIR0
\(^{74}\)Ge	87 K	ENDF/B–VIIIR0
\(^{74}\)Ge	296 K	ENDF/B–VIIIR0
\(^{76}\)Ge	87 K	ENDF/B–VIIIR0
\(^{76}\)Ge	296 K	ENDF/B–VIIIR0
\(^{75}\)As	87 K	ENDF/B–VIIIR0
\(^{75}\)As	296 K	ENDF/B–VIIIR0
\(^{74}\)Se	87 K	ENDF/B–VIIIR0
\(^{74}\)Se	296 K	ENDF/B–VIIIR0
\(^{76}\)Se	87 K	ENDF/B–VIIIR0
\(^{76}\)Se	296 K	ENDF/B–VIIIR0
\(^{77}\)Se	87 K	ENDF/B–VIIIR0
\(^{77}\)Se	296 K	ENDF/B–VIIIR0
\(^{78}\)Se	87 K	ENDF/B–VIIIR0
\(^{78}\)Se	296 K	ENDF/B–VIIIR0
\(^{80}\)Se	87 K	ENDF/B–VIIIR0
\(^{80}\)Se	296 K	ENDF/B–VIIIR0
\(^{82}\)Se	87 K	ENDF/B–VIIIR0
\(^{82}\)Se	296 K	ENDF/B–VIIIR0
\(^{79}\)Br	87 K	ENDF/B–VIIIR0
\(^{79}\)Br	296 K	ENDF/B–VIIIR0
\(^{81}\)Br	87 K	ENDF/B–VIIIR0
\(^{81}\)Br	296 K	ENDF/B–VIIIR0
\(^{78}\)Kr	87 K	ENDF/B–VIIIR0
\(^{78}\)Kr	296 K	ENDF/B–VIIIR0
\(^{80}\)Kr	87 K	ENDF/B–VIIIR0
\(^{80}\)Kr	296 K	ENDF/B–VIIIR0
\(^{82}\)Kr	87 K	ENDF/B–VIIIR0
\(^{82}\)Kr	296 K	ENDF/B–VIIIR0
\(^{83}\)Kr	87 K	ENDF/B–VIIIR0
\(^{83}\)Kr	296 K	ENDF/B–VIIIR0
\(^{84}\)Kr	87 K	ENDF/B–VIIIR0
\(^{84}\)Kr	296 K	ENDF/B–VIIIR0
\(^{86}\)Kr	87 K	ENDF/B–VIIIR0
\(^{86}\)Kr	296 K	ENDF/B–VIIIR0
\(^{85}\)Rb	87 K	ENDF/B–VIIIR0
\(^{85}\)Rb	296 K	ENDF/B–VIIIR0
\(^{87}\)Rb	87 K	ENDF/B–VIIIR0
\(^{87}\)Rb	296 K	ENDF/B–VIIIR0
\(^{84}\)Sr	87 K	ENDF/B–VIIIR0
\(^{84}\)Sr	296 K	ENDF/B–VIIIR0
\(^{86}\)Sr	87 K	ENDF/B–VIIIR0
\(^{86}\)Sr	296 K	ENDF/B–VIIIR0
\(^{87}\)Sr	87 K	ENDF/B–VIIIR0
\(^{87}\)Sr	296 K	ENDF/B–VIIIR0
\(^{88}\)Sr	87 K	ENDF/B–VIIIR0
\(^{88}\)Sr	296 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{90}\)Sr	87 K	ENDF/B–VIIIR0
\(^{90}\)Sr	296 K	ENDF/B–VIIIR0
\(^{89}\)Y	87 K	ENDF/B–VIIIR0
\(^{89}\)Y	296 K	ENDF/B–VIIIR0
\(^{90}\)Zr	87 K	ENDF/B–VIIIR0
\(^{90}\)Zr	296 K	ENDF/B–VIIIR0
\(^{91}\)Zr	87 K	ENDF/B–VIIIR0
\(^{91}\)Zr	296 K	ENDF/B–VIIIR0
\(^{92}\)Zr	87 K	ENDF/B–VIIIR0
\(^{92}\)Zr	296 K	ENDF/B–VIIIR0
\(^{94}\)Zr	87 K	ENDF/B–VIIIR0
\(^{94}\)Zr	296 K	ENDF/B–VIIIR0
\(^{96}\)Zr	87 K	ENDF/B–VIIIR0
\(^{96}\)Zr	296 K	ENDF/B–VIIIR0
\(^{93}\)Nb	87 K	ENDF/B–VIIIR0
\(^{93}\)Nb	296 K	ENDF/B–VIIIR0
\(^{92}\)Mo	87 K	ENDF/B–VIIIR0
\(^{92}\)Mo	296 K	ENDF/B–VIIIR0
\(^{94}\)Mo	87 K	ENDF/B–VIIIR0
\(^{94}\)Mo	296 K	ENDF/B–VIIIR0
\(^{95}\)Mo	87 K	ENDF/B–VIIIR0
\(^{95}\)Mo	296 K	ENDF/B–VIIIR0
\(^{96}\)Mo	87 K	ENDF/B–VIIIR0
\(^{96}\)Mo	296 K	ENDF/B–VIIIR0
\(^{97}\)Mo	87 K	ENDF/B–VIIIR0
\(^{97}\)Mo	296 K	ENDF/B–VIIIR0
\(^{98}\)Mo	87 K	ENDF/B–VIIIR0
\(^{98}\)Mo	296 K	ENDF/B–VIIIR0
\(^{100}\)Mo	87 K	ENDF/B–VIIIR0
\(^{100}\)Mo	296 K	ENDF/B–VIIIR0
\(^{99}\)Tc	87 K	ENDF/B–VIIIR0
\(^{99}\)Tc	296 K	ENDF/B–VIIIR0
\(^{96}\)Ru	87 K	ENDF/B–VIIIR0
\(^{96}\)Ru	296 K	ENDF/B–VIIIR0
\(^{98}\)Ru	87 K	ENDF/B–VIIIR0
\(^{98}\)Ru	296 K	ENDF/B–VIIIR0
\(^{99}\)Ru	87 K	ENDF/B–VIIIR0
\(^{99}\)Ru	296 K	ENDF/B–VIIIR0
\(^{100}\)Ru	87 K	ENDF/B–VIIIR0
\(^{100}\)Ru	296 K	ENDF/B–VIIIR0
\(^{101}\)Ru	87 K	ENDF/B–VIIIR0
\(^{101}\)Ru	296 K	ENDF/B–VIIIR0
\(^{102}\)Ru	87 K	ENDF/B–VIIIR0
\(^{102}\)Ru	296 K	ENDF/B–VIIIR0
\(^{104}\)Ru	87 K	ENDF/B–VIIIR0
\(^{104}\)Ru	296 K	ENDF/B–VIIIR0
\(^{103}\)Rh	87 K	ENDF/B–VIIIR0
\(^{103}\)Rh	296 K	ENDF/B–VIIIR0
\(^{102}\)Pd	87 K	ENDF/B–VIIIR0
\(^{102}\)Pd	296 K	ENDF/B–VIIIR0
\(^{104}\)Pd	87 K	ENDF/B–VIIIR0
\(^{104}\)Pd	296 K	ENDF/B–VIIIR0
\(^{105}\)Pd	87 K	ENDF/B–VIIIR0
\(^{105}\)Pd	296 K	ENDF/B–VIIIR0
\(^{106}\)Pd	87 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{106}\)Pd	296 K	ENDF/B–VIIIR0
\(^{108}\)Pd	87 K	ENDF/B–VIIIR0
\(^{108}\)Pd	296 K	ENDF/B–VIIIR0
\(^{110}\)Pd	87 K	ENDF/B–VIIIR0
\(^{110}\)Pd	296 K	ENDF/B–VIIIR0
\(^{107}\)Ag	87 K	ENDF/B–VIIIR0
\(^{107}\)Ag	296 K	ENDF/B–VIIIR0
\(^{109}\)Ag	87 K	ENDF/B–VIIIR0
\(^{109}\)Ag	296 K	ENDF/B–VIIIR0
\(^{106}\)Cd	87 K	ENDF/B–VIIIR0
\(^{106}\)Cd	296 K	ENDF/B–VIIIR0
\(^{108}\)Cd	87 K	ENDF/B–VIIIR0
\(^{108}\)Cd	296 K	ENDF/B–VIIIR0
\(^{110}\)Cd	87 K	ENDF/B–VIIIR0
\(^{110}\)Cd	296 K	ENDF/B–VIIIR0
\(^{111}\)Cd	87 K	ENDF/B–VIIIR0
\(^{111}\)Cd	296 K	ENDF/B–VIIIR0
\(^{112}\)Cd	87 K	ENDF/B–VIIIR0
\(^{112}\)Cd	296 K	ENDF/B–VIIIR0
\(^{113}\)Cd	87 K	ENDF/B–VIIIR0
\(^{113}\)Cd	296 K	ENDF/B–VIIIR0
\(^{114}\)Cd	87 K	ENDF/B–VIIIR0
\(^{114}\)Cd	296 K	ENDF/B–VIIIR0
\(^{116}\)Cd	87 K	ENDF/B–VIIIR0
\(^{116}\)Cd	296 K	ENDF/B–VIIIR0
\(^{113}\)In	87 K	ENDF/B–VIIIR0
\(^{113}\)In	296 K	ENDF/B–VIIIR0
\(^{115}\)In	87 K	ENDF/B–VIIIR0
\(^{115}\)In	296 K	ENDF/B–VIIIR0
\(^{112}\)Sn	87 K	ENDF/B–VIIIR0
\(^{112}\)Sn	296 K	ENDF/B–VIIIR0
\(^{114}\)Sn	87 K	ENDF/B–VIIIR0
\(^{114}\)Sn	296 K	ENDF/B–VIIIR0
\(^{115}\)Sn	87 K	ENDF/B–VIIIR0
\(^{115}\)Sn	296 K	ENDF/B–VIIIR0
\(^{116}\)Sn	87 K	ENDF/B–VIIIR0
\(^{116}\)Sn	296 K	ENDF/B–VIIIR0
\(^{117}\)Sn	87 K	ENDF/B–VIIIR0
\(^{117}\)Sn	296 K	ENDF/B–VIIIR0
\(^{118}\)Sn	87 K	ENDF/B–VIIIR0
\(^{118}\)Sn	296 K	ENDF/B–VIIIR0
\(^{119}\)Sn	87 K	ENDF/B–VIIIR0
\(^{119}\)Sn	296 K	ENDF/B–VIIIR0
\(^{120}\)Sn	87 K	ENDF/B–VIIIR0
\(^{120}\)Sn	296 K	ENDF/B–VIIIR0
\(^{122}\)Sn	87 K	ENDF/B–VIIIR0
\(^{122}\)Sn	296 K	ENDF/B–VIIIR0
\(^{124}\)Sn	87 K	ENDF/B–VIIIR0
\(^{124}\)Sn	296 K	ENDF/B–VIIIR0
\(^{121}\)Sb	87 K	ENDF/B–VIIIR0
\(^{121}\)Sb	296 K	ENDF/B–VIIIR0
\(^{123}\)Sb	87 K	ENDF/B–VIIIR0
\(^{123}\)Sb	296 K	ENDF/B–VIIIR0
\(^{120}\)Te	87 K	ENDF/B–VIIIR0
\(^{120}\)Te	296 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{122}\)Te	87 K	ENDF/B–VIIIR0
\(^{122}\)Te	296 K	ENDF/B–VIIIR0
\(^{123}\)Te	87 K	ENDF/B–VIIIR0
\(^{123}\)Te	296 K	ENDF/B–VIIIR0
\(^{124}\)Te	87 K	ENDF/B–VIIIR0
\(^{124}\)Te	296 K	ENDF/B–VIIIR0
\(^{125}\)Te	87 K	ENDF/B–VIIIR0
\(^{125}\)Te	296 K	ENDF/B–VIIIR0
\(^{126}\)Te	87 K	ENDF/B–VIIIR0
\(^{126}\)Te	296 K	ENDF/B–VIIIR0
\(^{128}\)Te	87 K	ENDF/B–VIIIR0
\(^{128}\)Te	296 K	ENDF/B–VIIIR0
\(^{130}\)Te	87 K	ENDF/B–VIIIR0
\(^{130}\)Te	296 K	ENDF/B–VIIIR0
\(^{127}\)I	87 K	ENDF/B–VIIIR0
\(^{127}\)I	296 K	ENDF/B–VIIIR0
\(^{129}\)I	4 K	ENDF/B–VIIIR0
\(^{129}\)I	87 K	ENDF/B–VIIIR0
\(^{129}\)I	296 K	ENDF/B–VIIIR0
\(^{129}\)I	430 K	ENDF/B–VIIIR0
\(^{129}\)I	686 K	ENDF/B–VIIIR0
\(^{131}\)I	4 K	ENDF/B–VIIIR0
\(^{131}\)I	87 K	ENDF/B–VIIIR0
\(^{131}\)I	296 K	ENDF/B–VIIIR0
\(^{131}\)I	430 K	ENDF/B–VIIIR0
\(^{131}\)I	686 K	ENDF/B–VIIIR0
\(^{135}\)I	4 K	ENDF/B–VIIIR0
\(^{135}\)I	87 K	ENDF/B–VIIIR0
\(^{135}\)I	296 K	ENDF/B–VIIIR0
\(^{135}\)I	430 K	ENDF/B–VIIIR0
\(^{135}\)I	686 K	ENDF/B–VIIIR0
\(^{124}\)Xe	87 K	ENDF/B–VIIIR0
\(^{124}\)Xe	296 K	ENDF/B–VIIIR0
\(^{126}\)Xe	87 K	ENDF/B–VIIIR0
\(^{126}\)Xe	296 K	ENDF/B–VIIIR0
\(^{128}\)Xe	87 K	ENDF/B–VIIIR0
\(^{128}\)Xe	296 K	ENDF/B–VIIIR0
\(^{129}\)Xe	87 K	ENDF/B–VIIIR0
\(^{129}\)Xe	296 K	ENDF/B–VIIIR0
\(^{130}\)Xe	87 K	ENDF/B–VIIIR0
\(^{130}\)Xe	296 K	ENDF/B–VIIIR0
\(^{131}\)Xe	87 K	ENDF/B–VIIIR0
\(^{131}\)Xe	296 K	ENDF/B–VIIIR0
\(^{132}\)Xe	87 K	ENDF/B–VIIIR0
\(^{132}\)Xe	296 K	ENDF/B–VIIIR0
\(^{134}\)Xe	87 K	ENDF/B–VIIIR0
\(^{134}\)Xe	296 K	ENDF/B–VIIIR0
\(^{135}\)Xe	4 K	ENDF/B–VIIIR0
\(^{135}\)Xe	87 K	ENDF/B–VIIIR0
\(^{135}\)Xe	296 K	ENDF/B–VIIIR0
\(^{135}\)Xe	430 K	ENDF/B–VIIIR0
\(^{135}\)Xe	686 K	ENDF/B–VIIIR0
\(^{136}\)Xe	87 K	ENDF/B–VIIIR0
\(^{136}\)Xe	296 K	ENDF/B–VIIIR0
\(^{133}\)Cs	87 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{133}\)Cs	296 K	ENDF/B–VIIIR0
\(^{135}\)Cs	4 K	ENDF/B–VIIIR0
\(^{135}\)Cs	87 K	ENDF/B–VIIIR0
\(^{135}\)Cs	296 K	ENDF/B–VIIIR0
\(^{135}\)Cs	430 K	ENDF/B–VIIIR0
\(^{135}\)Cs	686 K	ENDF/B–VIIIR0
\(^{136}\)Cs	4 K	ENDF/B–VIIIR0
\(^{136}\)Cs	87 K	ENDF/B–VIIIR0
\(^{136}\)Cs	296 K	ENDF/B–VIIIR0
\(^{136}\)Cs	430 K	ENDF/B–VIIIR0
\(^{136}\)Cs	686 K	ENDF/B–VIIIR0
\(^{130}\)Ba	87 K	ENDF/B–VIIIR0
\(^{130}\)Ba	296 K	ENDF/B–VIIIR0
\(^{132}\)Ba	87 K	ENDF/B–VIIIR0
\(^{132}\)Ba	296 K	ENDF/B–VIIIR0
\(^{134}\)Ba	87 K	ENDF/B–VIIIR0
\(^{134}\)Ba	296 K	ENDF/B–VIIIR0
\(^{135}\)Ba	87 K	ENDF/B–VIIIR0
\(^{135}\)Ba	296 K	ENDF/B–VIIIR0
\(^{136}\)Ba	87 K	ENDF/B–VIIIR0
\(^{136}\)Ba	296 K	ENDF/B–VIIIR0
\(^{137}\)Ba	87 K	ENDF/B–VIIIR0
\(^{137}\)Ba	296 K	ENDF/B–VIIIR0
\(^{138}\)Ba	87 K	ENDF/B–VIIIR0
\(^{138}\)Ba	296 K	ENDF/B–VIIIR0
\(^{138}\)La	87 K	ENDF/B–VIIIR0
\(^{138}\)La	296 K	ENDF/B–VIIIR0
\(^{139}\)La	87 K	ENDF/B–VIIIR0
\(^{139}\)La	296 K	ENDF/B–VIIIR0
\(^{136}\)Ce	87 K	ENDF/B–VIIIR0
\(^{136}\)Ce	296 K	ENDF/B–VIIIR0
\(^{138}\)Ce	87 K	ENDF/B–VIIIR0
\(^{138}\)Ce	296 K	ENDF/B–VIIIR0
\(^{140}\)Ce	87 K	ENDF/B–VIIIR0
\(^{140}\)Ce	296 K	ENDF/B–VIIIR0
\(^{142}\)Ce	87 K	ENDF/B–VIIIR0
\(^{142}\)Ce	296 K	ENDF/B–VIIIR0
\(^{141}\)Pr	87 K	ENDF/B–VIIIR0
\(^{141}\)Pr	296 K	ENDF/B–VIIIR0
\(^{142}\)Nd	87 K	ENDF/B–VIIIR0
\(^{142}\)Nd	296 K	ENDF/B–VIIIR0
\(^{143}\)Nd	87 K	ENDF/B–VIIIR0
\(^{143}\)Nd	296 K	ENDF/B–VIIIR0
\(^{144}\)Nd	87 K	ENDF/B–VIIIR0
\(^{144}\)Nd	296 K	ENDF/B–VIIIR0
\(^{145}\)Nd	87 K	ENDF/B–VIIIR0
\(^{145}\)Nd	296 K	ENDF/B–VIIIR0
\(^{146}\)Nd	87 K	ENDF/B–VIIIR0
\(^{146}\)Nd	296 K	ENDF/B–VIIIR0
\(^{148}\)Nd	87 K	ENDF/B–VIIIR0
\(^{148}\)Nd	296 K	ENDF/B–VIIIR0
\(^{150}\)Nd	87 K	ENDF/B–VIIIR0
\(^{150}\)Nd	296 K	ENDF/B–VIIIR0
\(^{145}\)Pm	87 K	ENDF/B–VIIIR0
\(^{145}\)Pm	296 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{144}\)Sm	87 K	ENDF/B–VIIIR0
\(^{144}\)Sm	296 K	ENDF/B–VIIIR0
\(^{147}\)Sm	87 K	ENDF/B–VIIIR0
\(^{147}\)Sm	296 K	ENDF/B–VIIIR0
\(^{148}\)Sm	87 K	ENDF/B–VIIIR0
\(^{148}\)Sm	296 K	ENDF/B–VIIIR0
\(^{149}\)Sm	87 K	ENDF/B–VIIIR0
\(^{149}\)Sm	296 K	ENDF/B–VIIIR0
\(^{150}\)Sm	87 K	ENDF/B–VIIIR0
\(^{150}\)Sm	296 K	ENDF/B–VIIIR0
\(^{152}\)Sm	87 K	ENDF/B–VIIIR0
\(^{152}\)Sm	296 K	ENDF/B–VIIIR0
\(^{154}\)Sm	87 K	ENDF/B–VIIIR0
\(^{154}\)Sm	296 K	ENDF/B–VIIIR0
\(^{151}\)Eu	87 K	ENDF/B–VIIIR0
\(^{151}\)Eu	296 K	ENDF/B–VIIIR0
\(^{153}\)Eu	87 K	ENDF/B–VIIIR0
\(^{153}\)Eu	296 K	ENDF/B–VIIIR0
\(^{152}\)Gd	87 K	ENDF/B–VIIIR0
\(^{152}\)Gd	296 K	ENDF/B–VIIIR0
\(^{154}\)Gd	87 K	ENDF/B–VIIIR0
\(^{154}\)Gd	296 K	ENDF/B–VIIIR0
\(^{155}\)Gd	87 K	ENDF/B–VIIIR0
\(^{155}\)Gd	296 K	ENDF/B–VIIIR0
\(^{156}\)Gd	87 K	ENDF/B–VIIIR0
\(^{156}\)Gd	296 K	ENDF/B–VIIIR0
\(^{157}\)Gd	87 K	ENDF/B–VIIIR0
\(^{157}\)Gd	296 K	ENDF/B–VIIIR0
\(^{158}\)Gd	87 K	ENDF/B–VIIIR0
\(^{158}\)Gd	296 K	ENDF/B–VIIIR0
\(^{160}\)Gd	87 K	ENDF/B–VIIIR0
\(^{160}\)Gd	296 K	ENDF/B–VIIIR0
\(^{159}\)Tb	87 K	ENDF/B–VIIIR0
\(^{159}\)Tb	296 K	ENDF/B–VIIIR0
\(^{156}\)Dy	87 K	ENDF/B–VIIIR0
\(^{156}\)Dy	296 K	ENDF/B–VIIIR0
\(^{158}\)Dy	87 K	ENDF/B–VIIIR0
\(^{158}\)Dy	296 K	ENDF/B–VIIIR0
\(^{160}\)Dy	87 K	ENDF/B–VIIIR0
\(^{160}\)Dy	296 K	ENDF/B–VIIIR0
\(^{161}\)Dy	87 K	ENDF/B–VIIIR0
\(^{161}\)Dy	296 K	ENDF/B–VIIIR0
\(^{162}\)Dy	87 K	ENDF/B–VIIIR0
\(^{162}\)Dy	296 K	ENDF/B–VIIIR0
\(^{163}\)Dy	87 K	ENDF/B–VIIIR0
\(^{163}\)Dy	296 K	ENDF/B–VIIIR0
\(^{164}\)Dy	87 K	ENDF/B–VIIIR0
\(^{164}\)Dy	296 K	ENDF/B–VIIIR0
\(^{165}\)Ho	87 K	ENDF/B–VIIIR0
\(^{165}\)Ho	296 K	ENDF/B–VIIIR0
\(^{162}\)Er	87 K	ENDF/B–VIIIR0
\(^{162}\)Er	296 K	ENDF/B–VIIIR0
\(^{164}\)Er	87 K	ENDF/B–VIIIR0
\(^{164}\)Er	296 K	ENDF/B–VIIIR0
\(^{166}\)Er	87 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{166}\)Er	296 K	ENDF/B–VIIIR0
\(^{167}\)Er	87 K	ENDF/B–VIIIR0
\(^{167}\)Er	296 K	ENDF/B–VIIIR0
\(^{168}\)Er	87 K	ENDF/B–VIIIR0
\(^{168}\)Er	296 K	ENDF/B–VIIIR0
\(^{170}\)Er	87 K	ENDF/B–VIIIR0
\(^{170}\)Er	296 K	ENDF/B–VIIIR0
\(^{169}\)Tm	87 K	TENDL–19
\(^{169}\)Tm	296 K	TENDL–19
\(^{168}\)Yb	87 K	ENDF/B–VIIIR0
\(^{168}\)Yb	296 K	ENDF/B–VIIIR0
\(^{170}\)Yb	87 K	ENDF/B–VIIIR0
\(^{170}\)Yb	296 K	ENDF/B–VIIIR0
\(^{171}\)Yb	87 K	ENDF/B–VIIIR0
\(^{171}\)Yb	296 K	ENDF/B–VIIIR0
\(^{172}\)Yb	87 K	ENDF/B–VIIIR0
\(^{172}\)Yb	296 K	ENDF/B–VIIIR0
\(^{173}\)Yb	87 K	ENDF/B–VIIIR0
\(^{173}\)Yb	296 K	ENDF/B–VIIIR0
\(^{174}\)Yb	87 K	ENDF/B–VIIIR0
\(^{174}\)Yb	296 K	ENDF/B–VIIIR0
\(^{176}\)Yb	87 K	ENDF/B–VIIIR0
\(^{176}\)Yb	296 K	ENDF/B–VIIIR0
\(^{175}\)Lu	87 K	TENDL–19
\(^{175}\)Lu	296 K	TENDL–19
\(^{176}\)Lu	87 K	TENDL–19
\(^{176}\)Lu	296 K	TENDL–19
\(^{174}\)Hf	87 K	ENDF/B–VIIIR0
\(^{174}\)Hf	296 K	ENDF/B–VIIIR0
\(^{176}\)Hf	87 K	ENDF/B–VIIIR0
\(^{176}\)Hf	296 K	ENDF/B–VIIIR0
\(^{177}\)Hf	87 K	ENDF/B–VIIIR0
\(^{177}\)Hf	296 K	ENDF/B–VIIIR0
\(^{178}\)Hf	87 K	ENDF/B–VIIIR0
\(^{178}\)Hf	296 K	ENDF/B–VIIIR0
\(^{179}\)Hf	87 K	ENDF/B–VIIIR0
\(^{179}\)Hf	296 K	ENDF/B–VIIIR0
\(^{180}\)Hf	87 K	ENDF/B–VIIIR0
\(^{180}\)Hf	296 K	ENDF/B–VIIIR0
\(^{180m}\)Ta	87 K	TENDL–19
\(^{180m}\)Ta	296 K	TENDL–19
\(^{181}\)Ta	87 K	ENDF/B–VIIIR0
\(^{181}\)Ta	296 K	ENDF/B–VIIIR0
\(^{180}\)W	4 K	ENDF/B–VIIIR0
\(^{180}\)W	87 K	ENDF/B–VIIIR0
\(^{180}\)W	296 K	ENDF/B–VIIIR0
\(^{180}\)W	430 K	ENDF/B–VIIIR0
\(^{180}\)W	686 K	ENDF/B–VIIIR0
\(^{182}\)W	4 K	ENDF/B–VIIIR0
\(^{182}\)W	87 K	ENDF/B–VIIIR0
\(^{182}\)W	296 K	ENDF/B–VIIIR0
\(^{182}\)W	430 K	ENDF/B–VIIIR0
\(^{182}\)W	686 K	ENDF/B–VIIIR0
\(^{183}\)W	4 K	ENDF/B–VIIIR0
\(^{183}\)W	87 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{183}\)W	296 K	ENDF/B–VIIIR0
\(^{183}\)W	430 K	ENDF/B–VIIIR0
\(^{183}\)W	686 K	ENDF/B–VIIIR0
\(^{184}\)W	4 K	ENDF/B–VIIIR0
\(^{184}\)W	87 K	ENDF/B–VIIIR0
\(^{184}\)W	296 K	ENDF/B–VIIIR0
\(^{184}\)W	430 K	ENDF/B–VIIIR0
\(^{184}\)W	686 K	ENDF/B–VIIIR0
\(^{186}\)W	4 K	ENDF/B–VIIIR0
\(^{186}\)W	87 K	ENDF/B–VIIIR0
\(^{186}\)W	296 K	ENDF/B–VIIIR0
\(^{186}\)W	430 K	ENDF/B–VIIIR0
\(^{186}\)W	686 K	ENDF/B–VIIIR0
\(^{185}\)Re	87 K	ENDF/B–VIIIR0
\(^{185}\)Re	296 K	ENDF/B–VIIIR0
\(^{187}\)Re	87 K	ENDF/B–VIIIR0
\(^{187}\)Re	296 K	ENDF/B–VIIIR0
\(^{184}\)Os	87 K	ENDF/B–VIIIR0
\(^{184}\)Os	296 K	ENDF/B–VIIIR0
\(^{186}\)Os	87 K	ENDF/B–VIIIR0
\(^{186}\)Os	296 K	ENDF/B–VIIIR0
\(^{187}\)Os	87 K	ENDF/B–VIIIR0
\(^{187}\)Os	296 K	ENDF/B–VIIIR0
\(^{188}\)Os	87 K	ENDF/B–VIIIR0
\(^{188}\)Os	296 K	ENDF/B–VIIIR0
\(^{189}\)Os	87 K	ENDF/B–VIIIR0
\(^{189}\)Os	296 K	ENDF/B–VIIIR0
\(^{190}\)Os	87 K	ENDF/B–VIIIR0
\(^{190}\)Os	296 K	ENDF/B–VIIIR0
\(^{192}\)Os	87 K	ENDF/B–VIIIR0
\(^{192}\)Os	296 K	ENDF/B–VIIIR0
\(^{191}\)Ir	87 K	ENDF/B–VIIIR0
\(^{191}\)Ir	296 K	ENDF/B–VIIIR0
\(^{193}\)Ir	87 K	ENDF/B–VIIIR0
\(^{193}\)Ir	296 K	ENDF/B–VIIIR0
\(^{190}\)Pt	87 K	ENDF/B–VIIIR0
\(^{190}\)Pt	296 K	ENDF/B–VIIIR0
\(^{192}\)Pt	87 K	ENDF/B–VIIIR0
\(^{192}\)Pt	296 K	ENDF/B–VIIIR0
\(^{194}\)Pt	87 K	ENDF/B–VIIIR0
\(^{194}\)Pt	296 K	ENDF/B–VIIIR0
\(^{195}\)Pt	87 K	ENDF/B–VIIIR0
\(^{195}\)Pt	296 K	ENDF/B–VIIIR0
\(^{196}\)Pt	87 K	ENDF/B–VIIIR0
\(^{196}\)Pt	296 K	ENDF/B–VIIIR0
\(^{198}\)Pt	87 K	ENDF/B–VIIIR0
\(^{198}\)Pt	296 K	ENDF/B–VIIIR0
\(^{197}\)Au	87 K	ENDF/B–VIIIR0
\(^{197}\)Au	296 K	ENDF/B–VIIIR0
\(^{196}\)Hg	87 K	ENDF/B–VIIIR0
\(^{196}\)Hg	296 K	ENDF/B–VIIIR0
\(^{198}\)Hg	87 K	ENDF/B–VIIIR0
\(^{198}\)Hg	296 K	ENDF/B–VIIIR0
\(^{199}\)Hg	87 K	ENDF/B–VIIIR0
\(^{199}\)Hg	296 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{200}\)Hg	87 K	ENDF/B–VIIIR0
\(^{200}\)Hg	296 K	ENDF/B–VIIIR0
\(^{201}\)Hg	87 K	ENDF/B–VIIIR0
\(^{201}\)Hg	296 K	ENDF/B–VIIIR0
\(^{202}\)Hg	87 K	ENDF/B–VIIIR0
\(^{202}\)Hg	296 K	ENDF/B–VIIIR0
\(^{204}\)Hg	87 K	ENDF/B–VIIIR0
\(^{204}\)Hg	296 K	ENDF/B–VIIIR0
\(^{203}\)Tl	87 K	ENDF/B–VIIIR0
\(^{203}\)Tl	296 K	ENDF/B–VIIIR0
\(^{205}\)Tl	87 K	ENDF/B–VIIIR0
\(^{205}\)Tl	296 K	ENDF/B–VIIIR0
\(^{204}\)Pb	4 K	TENDL–19
\(^{204}\)Pb	87 K	TENDL–19
\(^{204}\)Pb	296 K	TENDL–19
\(^{204}\)Pb	430 K	TENDL–19
\(^{204}\)Pb	686 K	TENDL–19
\(^{206}\)Pb	4 K	TENDL–19
\(^{206}\)Pb	87 K	TENDL–19
\(^{206}\)Pb	296 K	TENDL–19
\(^{206}\)Pb	430 K	TENDL–19
\(^{206}\)Pb	686 K	TENDL–19
\(^{207}\)Pb	4 K	TENDL–19
\(^{207}\)Pb	87 K	TENDL–19
\(^{207}\)Pb	296 K	TENDL–19
\(^{207}\)Pb	430 K	TENDL–19
\(^{207}\)Pb	686 K	TENDL–19
\(^{208}\)Pb	4 K	ENDF/B–VIIIR0
\(^{208}\)Pb	87 K	ENDF/B–VIIIR0
\(^{208}\)Pb	296 K	ENDF/B–VIIIR0
\(^{208}\)Pb	430 K	ENDF/B–VIIIR0
\(^{208}\)Pb	686 K	ENDF/B–VIIIR0
\(^{209}\)Bi	4 K	ENDF/B–VIIIR0
\(^{209}\)Bi	87 K	ENDF/B–VIIIR0
\(^{209}\)Bi	296 K	ENDF/B–VIIIR0
\(^{209}\)Bi	430 K	ENDF/B–VIIIR0
\(^{209}\)Bi	686 K	ENDF/B–VIIIR0
\(^{226}\)Ra	87 K	TENDL–19
\(^{226}\)Ra	296 K	TENDL–19
\(^{227}\)Ac	87 K	TENDL–19
\(^{227}\)Ac	296 K	TENDL–19
\(^{230}\)Th	87 K	ENDF/B–VIIR1
\(^{230}\)Th	296 K	ENDF/B–VIIR1
\(^{230}\)Th	87 K	ENDF/B–VIIIR0
\(^{230}\)Th	296 K	ENDF/B–VIIIR0
\(^{232}\)Th	4 K	ENDF/B–VIIIR0
\(^{232}\)Th	87 K	ENDF/B–VIIIR0
\(^{232}\)Th	296 K	ENDF/B–VIIIR0
\(^{232}\)Th	430 K	ENDF/B–VIIIR0
\(^{232}\)Th	686 K	ENDF/B–VIIIR0
\(^{233}\)Th	4 K	ENDF/B–VIIIR0
\(^{233}\)Th	87 K	ENDF/B–VIIIR0
\(^{233}\)Th	296 K	ENDF/B–VIIIR0
\(^{233}\)Th	430 K	ENDF/B–VIIIR0
\(^{233}\)Th	686 K	ENDF/B–VIIIR0

Isotope	Temperature	Source

\(^{231}\)Pa	87 K	ENDF/B–VIIIR0
\(^{231}\)Pa	296 K	ENDF/B–VIIIR0
\(^{233}\)Pa	87 K	ENDF/B–VIIIR0
\(^{233}\)Pa	296 K	ENDF/B–VIIIR0
\(^{233}\)U	4 K	ENDF/B–VIIIR0
\(^{233}\)U	87 K	ENDF/B–VIIIR0
\(^{233}\)U	296 K	ENDF/B–VIIIR0
\(^{233}\)U	430 K	ENDF/B–VIIIR0
\(^{233}\)U	686 K	ENDF/B–VIIIR0
\(^{234}\)U	87 K	ENDF/B–VIIIR0
\(^{234}\)U	296 K	ENDF/B–VIIIR0
\(^{235}\)U	4 K	ENDF/B–VIIR1
\(^{235}\)U	87 K	ENDF/B–VIIR1
\(^{235}\)U	296 K	ENDF/B–VIIR1
\(^{235}\)U	430 K	ENDF/B–VIIR1
\(^{235}\)U	686 K	ENDF/B–VIIR1
\(^{235}\)U	4 K	ENDF/B–VIIIR0
\(^{235}\)U	87 K	ENDF/B–VIIIR0
\(^{235}\)U	296 K	ENDF/B–VIIIR0
\(^{235}\)U	430 K	ENDF/B–VIIIR0
\(^{235}\)U	686 K	ENDF/B–VIIIR0
\(^{236}\)U	87 K	ENDF/B–VIIIR0
\(^{236}\)U	296 K	ENDF/B–VIIIR0
\(^{237}\)U	87 K	ENDF/B–VIIIR0
\(^{237}\)U	296 K	ENDF/B–VIIIR0
\(^{238}\)U	4 K	ENDF/B–VIIR1
\(^{238}\)U	87 K	ENDF/B–VIIR1
\(^{238}\)U	296 K	ENDF/B–VIIR1
\(^{238}\)U	430 K	ENDF/B–VIIR1
\(^{238}\)U	686 K	ENDF/B–VIIR1
\(^{238}\)U	4 K	ENDF/B–VIIIR0
\(^{238}\)U	87 K	ENDF/B–VIIIR0
\(^{238}\)U	296 K	ENDF/B–VIIIR0
\(^{238}\)U	430 K	ENDF/B–VIIIR0
\(^{238}\)U	686 K	ENDF/B–VIIIR0
\(^{237}\)Np	87 K	ENDF/B–VIIIR0
\(^{237}\)Np	296 K	ENDF/B–VIIIR0
\(^{239}\)Np	87 K	TENDL–19
\(^{239}\)Np	296 K	TENDL–19
\(^{238}\)Pu	87 K	ENDF/B–VIIIR0
\(^{238}\)Pu	296 K	ENDF/B–VIIIR0
\(^{239}\)Pu	4 K	ENDF/B–VIIIR0
\(^{239}\)Pu	87 K	ENDF/B–VIIIR0
\(^{239}\)Pu	296 K	ENDF/B–VIIIR0
\(^{239}\)Pu	430 K	ENDF/B–VIIIR0
\(^{239}\)Pu	686 K	ENDF/B–VIIIR0
\(^{240}\)Pu	4 K	ENDF/B–VIIIR0
\(^{240}\)Pu	87 K	ENDF/B–VIIIR0
\(^{240}\)Pu	296 K	ENDF/B–VIIIR0
\(^{240}\)Pu	430 K	ENDF/B–VIIIR0
\(^{240}\)Pu	686 K	ENDF/B–VIIIR0
\(^{241}\)Pu	87 K	ENDF/B–VIIIR0
\(^{241}\)Pu	296 K	ENDF/B–VIIIR0
\(^{241}\)Am	87 K	ENDF/B–VIIIR0
\(^{241}\)Am	296 K	ENDF/B–VIIIR0