Online Catalog
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Click on Abstract to read the package abstract.
Click on RSICC Tapelist to view list of files distributed with package.

Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
FEDC -- US Government Agencies and Their Contractors Only
OECD -- Restricted/See Abstract
RUGA -- Restricted Use Government Authorized
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages with Keyword: CROSS SECTIONS
Package NameAbstractRSICC TapelistTitle
ADS-LIB/V2.0AbstractD00250 MNYCP 00Test Library for Accelerator Driven Systems V2.0
BERMUDAAbstractC00616 FV260 03Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors.
CEPXSAbstractC00837 MNYCP 00Coupled Electron-Photon Cross Section
CLESAbstractD00233 MNYCP 00Cross Section Library of Moderator Materials for Low-Energy Neutron Sources.
COG11.1AbstractC00829 MNYCP 00Multiparticle Monte Carlo Code System for Shielding and Criticality Use.
COV-15GROUP-2006AbstractD00232 MNYCP 0015-Group Cross Section Covariance Matrix Library.
DRAGON2PARTISNAbstractC00803 PCX86 00Cross-Sections Data Generation for PARTISN4.0.
DWBA07/DWBB07AbstractP00338 MNYCP 01Code System for Inelastic and Elastic Scattering with Nucleon-Nucleon Potential
FISPACT-II 5.0AbstractC00836 MNYCP 03FISPACT-II 5.0 & TENDL-2019; TENDL-2017, -2015; ENDF/B-VIII.0, -VII.1; JENDL-4.0; JEFF-3.3, -3.2; CENDL-3.1; HEIR-0.1; HEAD-2009; and GEFY-6.1 libraries.
FLUKA05-PRE-LIBAbstractD00260 PCX86 00FLUKA05 Multi-Group, Multi-Purpose Nuclear Data Library, Neutrons, Photons, Charged Particles.
FSXJ32AbstractD00244 MNYCP 00A Continuous Energy Cross Section MCNP Nuclear Data Library Based on JENDL-3.2.
GAKER-KIRAAbstractC00813 C3600 00Energy Transfer of Protons in H2O or Polyethylene and Deuterons in D2O.
GENP-2AbstractC00575 ALLMF 00Generalized Perturbation Theory Code System.
MATXSLIBJ33AbstractD00258 MNYCP 01JENDL-3.3 Based, 175 Neutron-42 Photon Groups (VITAMIN-J) MATXS Library for Discrete Ordinates Multi-Group Transport Codes.
MCNP6.2-EXE
810
AbstractC00850 MNYCP 01Monte Carlo N-Particle Transport Code System.
MCNP-DSP
810
AbstractC00699 MNYCP 00Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A.
MCNP-DSP-EXE
810
AbstractC00699 MNYCP 01Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A.
MCRACAbstractC00562 IBMPC 00Multiple Cycle Reactor Analysis Code.
MTR_PC 2.6AbstractC00674 PC386 00Modular Code System for Neutronics, Thermalhydraulics and Shielding Calculations.
MVP-GMVP IIAbstractC00739 MNYCP 00General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods.
PIXE2010AbstractD00246 MNYCP 00Proton/alpha Ionization (K, L, M shell), Tabulated Cross Section Library.
PRECO2006AbstractP00226 MNYCP 02Exciton Model Code System for Calculating Preequilibrium and Direct Double Differential Cross Sections.
RHEINAbstractC00585 I3090 00Reactor Code System for Neutron Physics Calculation.
RMET21AbstractC00597 D0VAX 00Detailed Space and Energy Treatment of Neutron Resonances for Homogeneous Mixtures and Cylinderized Reactor Cells.
SERPENT117-ACELIBAbstractD00249 MNYCP 00Continuous-Energy X-Sec Library, Radioactive Decay, Fission Yield Data for SERPENT in ACE.
TART2016AbstractC00638 MNYCP 08Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System.
TRIPOLI-4 8.1
OECD
AbstractC00806 MNYCP 00Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport Calculations.
TRIPOLI-4 9S
OECD
AbstractC00815 MNYCP 00Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport Calculations.
VITENDF70.BOLIBAbstractD00261 PCX86 00ENDF/B-VII.0 Multi-Group Coupled (199n +42gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications.
VITJEF22.BOLIBAbstractD00241 MNYCP 00JEF-2.2 Multigroup Coupled (199n + 42?) Cross-Section Library in AMPX Format for Nuclear Fission Applications.
VITJEFF311.BOLIBAbstractD00257 MNYCP 01JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Section Library in AMPX Format for Nuclear Fission Applications.
WIMS-ANL 4.0AbstractC00698 MNYCP 00Deterministic Code System for Reactor Lattice Calculation.
WIMSD-5B.12AbstractC00656 MNYCP 02Deterministic Code System for Reactor Lattice Calculation
XSUN-2013AbstractC00825 PCX86 00Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.