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Application Nuclear Data Libraries:
Continuous-, Energy-group-averaged, etc. for use with codes for radiation transport, reactor analysis depletion, dosimetry, and shielding
Distributed by the OECD/NEA Data Bank and RSICC
15 December 2003
Summary information on each item listed can be found by accessing the following two URLs:
http://www-rsicc.ornl.gov/rsic.html and http://www.oecd-nea.org/html/dbprog/
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Id. |
Name |
Description |
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Activation |
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activate2002 |
Activation Cross Section by Combining Cross Section and Multiplier, |
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aasy-2001 |
European Neutron Activation System |
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zz reac-2 |
nuclide activation & transmutation |
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zz activ-87 |
fast neutron activation cross-section |
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zz eaf 99 |
cross section library for neutron induced activation materials |
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zz gammon |
activation data library for fusion reaction |
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zz tpasgam-85 |
gamma spectra data library for activation analysis |
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zz montage-400 |
neutron activation 100-group cross-section library of fusion reactor materials |
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zz-ieaf-2001 |
intermediate energy activation file |
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zz-mcb-eaf99 |
MCB continuous energy neutron cross-section libraries T=300-1800K |
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zz ecpl86 |
data library of evaluated charged particle cross-section, nuclides up to oxygen |
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zz-mendl-2p |
proton medium energy nuclear data library |
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zz-elast2 |
database of cross sections for the elastic scattering of electrons and positrons by atoms |
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zz decayrem/c |
decay spectra library for EXREM calculation |
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nuchart |
nuclear properties & decay data chart |
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zz elecspec |
electron spectra data library from fission product decay |
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zz gamdat-78 |
gamma decay data of radioisotopes |
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zz damsig84 |
640-group damage cross-section library for SAND-2 calculation |
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zz doscros |
neutron cross-section library for spectra unfolding & integral parameter evaluation |
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zz dosdat-2 |
gamma & electron dose conversion factor data library for body organs |
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zz dosedat-doe |
Dose-rate conversion factors for external photon, electron exposure |
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zz dralist |
radioactive decay data for dosimetry & hazard assessment |
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zz fgr-dose |
dose coefficient for intake & exposure to radionuclides |
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zz irdf-82 |
620-group cross-section library & spectra for dosimetry calculation in ENDF-5 format |
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zz n-spect/det-resp |
neutron spectra & detector responses for radiation protection |
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zz nucdecay |
nuclear decay data for radiation dosimetry calculation for ICRP & MIRD |
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zz nucdecaycalc |
nuclear decay data for radiation dosimetry calculation for ICRP |
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zz raddecay |
decay data library for radiological assessment |
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zz rrdf-98 |
Cross-sections and covariance matrices for 22 neutron induced dosimetry reactions |
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zz snlrml |
dosimetry cross-section recommendations |
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zz thermgam |
thermal neutron capture gamma spectroscopical data library |
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zz unger |
effective dose equivalent data for selected isotopes |
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zz xg |
radionuclide decay parameters for gamma & x-ray detector calibration |
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zz-decdc |
nuclear decay data files for dose calculation |
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zz decaygam |
isotope gamma energy library for spectrometry evaluation |
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errorj |
Multigroup covariance matrices generation from ENDF/B-6 format |
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zz coverv |
multigroup cross-section covariance matrices in COVERX format |
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zz covfils |
30-group covariance library from ENDF/B-5 for sensitivity studies |
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zz senpro/45c |
multigroup sensitivity library for fast reactors, thermal reactors |
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zz vitamin j/cova |
covariance matrix data library for sensitivity analysis |
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zz doscov |
24-group covariance data library from ENDF/B-V for dosimetry calculation |
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zz covfils-2 |
74-group neutron cross-section, scattering matrices, covariances for fusion reactors |
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zz rrdf-98 |
Cross-sections and covariance matrices for 22 neutron induced dosimetry reactions |
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zz covfils-2-i |
74-group neutron cross-section ,scattering matrices, covariances for fusion reactors |
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zz barc-75 |
coupled 50 neutron-group 25 gamma-group cross-section library for 42 nuclides |
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zz cobb |
123 n-group cross-section library from ENDF/B for XSDRN calculation |
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zz scale-lib |
neutron-group constants library from JEF-1 using NPTXS, XLACS, XLACS-2 programs |
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zz vitamin-b6 |
fine-group cross-section library from ENDF/B-VI.3 for radiation transport |
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zz matxs10 |
30-group neutron, 12-group gamma cross-sections in MATXS format from ENDF/B-VI |
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zz matxs11 |
80-group neutron, 24-group gamma cross-section in MATXS format from ENDF/B-VI |
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zz-mcjef22nea.bolib |
MCNP cross section library based on JEF-2.2 many temperatures |
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zz-mcb63nea.bolib |
MCNP cross section library based on ENDF/B-VI.3 many temperatures |
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zz-mclib-e6 |
continuous energy cross section library from ENDF/B-VI.5 for MCNP-4A,-4B, 300K, 600K, 900K |
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zz mcnpxdata |
neutron, photon, and electron data libraries for MCNPX. |
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zz mcnpdata |
standard neutron, photon & electron data libraries for MCNP-4C and MCNP4C2 |
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zz fsxlibj33 |
MCNP nuclear data library based on JENDL-3.3 |
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zz mcnpxs |
neutron, photon cross-section data library from ENDF/B-V for MCNP-4B |
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zz anslv |
multigroup cross sections library for advanced neutron source reactor design studies |
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zz barc-27grp |
27-group infinitely dilute & Bondarenko cross-section library from ENDF/B |
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zz etog-1-data |
cross-section library for programs MUFT3, MUFT5, GAM1, GAM2 generated from ENDF/B |
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zz iran-lib |
multigroup neutron gamma cross-section library for 33 elements in ANISN format |
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zz lasl-xsecs |
fast & thermal multigroup cross-section library in LANL transport format |
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zz lump |
lumped fission product cross-section library for fast reactor anal from ENDF/B-V |
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zz matxs70-jeff87 |
69+1 group MATXS library in WIMS BOXER structure |
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zz tempest/muft |
thermal neutron & fast neutron multigroup cross-section library for program LEOPARD |
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zz thermos |
multigroup P0 to P5 thermal scattering kernels from ENDF/B scat law data |
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zz wimkal-88 |
69-group KAERI WIMS library for thermal reactors |
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zz wims-lib/jef87 |
69+1 group WIMS-D library from JEF-1 |
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zz- mcb-jef2.2 |
MCB continuous energy neutron cross-section libraries T=300-1800K |
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zz mcb-endf/b6.8 |
MCB continuous energy neutron cross-section libraries T=300-1800K |
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zz-mcb-jendl-3.2 |
MCB continuous energy neutron cross-section libraries T=300-1800K |
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zz-fsxj32 |
MCNP nuclear data library based on JENDL-3.2 |
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zz vitjef22.bolib |
JEF-2.2 multigroup coupled (199n + 42gamma) x-section lib. in AMPX format for nuclear fission applications |
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zz-utxs6 |
MCNP continuous energy neutron cross-section libraries T=300-1365K |
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Burnup / isotope buildup |
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zz actinides |
84-group neutron cross-section library for Pu242 to Es253 isotope production chain |
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zz oryx-e/38b |
group constant library from ENDF/B fission product data for ORIGEN calculation |
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zz-orlibj32 |
data libraries for ORIGEN2 code based on JENDL-3.2 |
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zz-candulib-aecl |
Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels |
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Fast reactors |
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zz cl50g |
50-group multigroup library in AMPX format for fast reactor calculation |
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zz jfs-1 |
cross-section library 25-groups ABBN & 70-group JFS for fast reactor calculation |
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zz lib-iv |
50-group cross-section library in CCCC-III format from ENDF/B-IV for fast reactors |
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zz microx 2 fss lib |
data library for fast spectrum systems analysis |
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zz sinex |
100 n-group neutron reaction cross-section library from ENDF/B by SUPERTOG for ANISN |
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zz-kafax-f22 |
80 and 24 neutron groups cross-section library in MATXS format based on JEF-2.2 for fast reactors |
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zz abbn |
26 group cross-sections & self shielding factors for fast reactors |
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zz amz |
70-group 40 isotope multigroup library for fast reactor calculation |
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zz airfewg |
gamma, neutron transport calculation in air using fewg1 cross-section |
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zz cad |
51 neutron-group, 25 gamma-group albedo data for 4 materials from DOT flux |
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zz dabl69 |
46-group neutron, 23-group gamma cross-section in ANISN format from ENDF/B-V |
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zz avker |
neutron kerma response function data library |
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zz ritts |
121-group coupled cross-section for ANISN, DOT, MORSE |
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zz air |
group constant library of secondary gamma transport in air for ANISN calculation |
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zz nox |
119-group coupled cross-section of nitrogen, oxygen, air for MORSE |
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zz nab |
100 n-group cross-section library of Na & al for ANISN, DOT, MORSE neutron transport |
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zz endlib |
coupled electron & photon transport library in ENDL format |
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zz fcxsec |
coupled cross-section library for shielding from VITAMIN-C in AMPX, ANISN format |
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zz geff1 |
175-group neutron cross-section in VITAMIN-J1 format for shielding benchmarks |
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zz kermal |
neutron & gamma kerma library from ENDL & EGDL |
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zz matxslibj33 |
JENDL-3.3 based,175 N-42 photon groups (VITAMIN-J) MATXS library for discrete ordinates multi-group |
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zz matx175/42-jeff87 |
172 neutron-group, 42 gamma-group MATXS library in VITAMIN-J structure |
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zz recoil/b |
heavy charged particle recoil spectra library for radiation damage calculation |
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zz rfl-2-dtf |
group constant library of reaction cross-section, gas production, kerma, dpa |
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zz sailor |
47 neutron-20 gamma-group coupled cross-section library from VITAMIN-C by AMPX |
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zz sigmna-a |
photon interaction & absorption cross-section library |
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zz vitamin-j/kerma |
gas production cross-sections, neutron & gamma kerma in FOURACES format |
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zz wm-nrsm |
neutron & gamma group cross-section library for nuclear rocket shielding calculations |
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zz-kashil-e6 |
175 neutron, 42 gamma groups cross sections in MATXS format based on ENDF/B-VI.5 for shielding |
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zz-macklib-4 |
171-neutron, 36-gamma group response function library from ENDF/B-IV |
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Accelerators / high energy |
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zz hilo86 |
66 neutron, 22 gamma group cross-section library for ANISN, DORT, MORSE |
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zz hilo86r |
66 neutron, 22 gamma group cross-section for 400 MeV neutron, 20 MeV gamma |
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zz la100 |
ENDF format data library for neutron & protons up to 100 MeV |
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zz lahimack |
multigroup neutron & gamma cross-section & response function up to 800 MeV |
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zz skyport |
importance function for neutron & gamma for skyshine dose from accelerator |
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zz pnesd |
diffusion elastic scattering cross-section of 3 MeV to 1000 MeV proton on natural isotopes |
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Fast spectra |
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zz dlc-13b |
resonance cross-section group constant library for tungsten & depleted Pu |
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zz gamlib |
99-group cross-section library by SUPERTOG calculation from ENDF/B |
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zz decnet-gendf |
fusion damage library of 175 neutron & 42 photon VITAMIN-J groups |
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zz dlc-28 |
73-group neutron & gamma coupled cross-section for CTR transport calculation |
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zz eff1lib |
fusion fast neutron data library for MCNP |
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zz epr/37f |
100 neutron-group, 21 gamma-group coupled cross-section for EPR fusion system |
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zz fsxlib-j3r2 |
evaluated nuclear data file from JENDL-3 for fusion neutronics |
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zz geff-2-gendf |
P5 175-neutron, 42-gamma library & P8 42-gamma library for fusion neutronics |
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zz geff-2-matxs |
coupled neutron-gamma fusion neutronics library in MATXS format |
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zz greac-ecn-3&4 |
neutron reaction cross-section library for fusion reactors |
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zz kaos/lib-v |
kerma factors, nuclear response function library for fission, fusion |
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zz macklib |
nuclear response function library for CTR & hybrid fission fusion system materials |
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zz shamsi |
coupled 43-neutron 14-gamma P3 cross-section library for fusion blanket or shield calculations |
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zz ukctr-1 |
cross-section library for neutron flux & neutron reaction rates in CTR calculation |
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zz ukctriiia |
n cross-section data library for fusion reactor mat activation |
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zz vitamin-c/b |
171 neutron-group, 36 gamma-group coupled cross-section for fusion, LMFBR calculations |
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zz vitamin-e |
174-group neutron ,38-group gamma cross-section in AMPX format |
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zz babel |
multigroup neutron cross-section data library for fast reactor shield calculation |
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Reactor shielding |
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zz bp-3 |
104-group neutron cross-section library for transport calculation |
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zz ampx-2/123 |
123-group neutron cross-section library from ENDF/B-4 by AMPX-2 |
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zz ampx01/27c |
coupled neutron-gamma group constant library by AMPX for transport calculation |
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zz clear/42b |
126 n-group, 36 gamma-group coupled cross-section in AMPX, CCCC format, for LMFBR |
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zz cask |
40-group neutron & gamma coupled cross-section for PWR shipping casks |
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zz dlc-2d/100g |
100 neutron-group cross-section library by SUPERTOG calculation for ANISN, DOT |
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zz dlc-31 |
37 neutron-group, 21 gamma-group coupled group constants library from ENDF/B |
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zz eurlib |
coupled neutron gamma multigroup cross-section library from ENDF/B for shielding calculation |
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zz fgxrrs |
10 n-group,7 gamma-group self-shielded cross-section in ANISN format |
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zz l26p3s34 |
26-group constants library of 34 materials for neutron shielding calculations |
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zz lafpx-v |
multigroup fission product data library from ENDF/B-V by program NJOY |
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zz sail |
albedo scattering data library for 3-d M-C radiation transport in LWR pressure vessel |
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zz ukfy2 |
fission yields of Th, U, Np, Pu, Am, Cm, Cf isotopes |
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zz-bugle-96 |
multigroup coupled neutron gamma cross-section for LWR shielding calculation |
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zz skysdata-ksu |
neutron and gamma skyshine responses |
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Photons, gamma-rays / X-rays |
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zz ans643 |
geometric progression gamma-ray buildup factor coefficient library |
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zz poplib |
secondary gamma yields & cross-section library for POPOP-4 calculation |
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zz storm-israel |
gamma interaction cross-section library in ENDF/B format for transport |
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zz hpice/f |
gamma interaction cross-section library in ENDF/B format for transport calculation |
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zz photx |
photon interaction cross-section library for 100 elements |
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zz pve |
38-group P8 photon cross-section library for gamma radiation transport |
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zz dlc-21 |
x-ray attenuation cross-section library from 0.1 keV to 1 MeV |
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zz xcom |
photon cross-section library for personal computer |
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