Click on Package Name to get detailed information.
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 Name | Abstract | RSICC Tapelist | Title |
| ADS-LIB/V2.0 | Abstract | D00250 MNYCP 00 | Test Library for Accelerator Driven Systems V2.0 |
| BERMUDA | Abstract | C00616 FV260 03 | Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors. |
| CEPXS | Abstract | C00837 MNYCP 00 | Coupled Electron-Photon Cross Section |
| CLES | Abstract | D00233 MNYCP 00 | Cross Section Library of Moderator Materials for Low-Energy Neutron Sources. |
| COG11.1 | Abstract | C00829 MNYCP 00 | Multiparticle Monte Carlo Code System for Shielding and Criticality Use. |
| COV-15GROUP-2006 | Abstract | D00232 MNYCP 00 | 15-Group Cross Section Covariance Matrix Library. |
| DRAGON2PARTISN | Abstract | C00803 PCX86 00 | Cross-Sections Data Generation for PARTISN4.0. |
| DWBA07/DWBB07 | Abstract | P00338 MNYCP 01 | Code System for Inelastic and Elastic Scattering with Nucleon-Nucleon Potential |
| FISPACT-II 5.0 | Abstract | C00836 MNYCP 03 | Inventory Simulation Platform for Nuclear Observables and Materials Science. |
| FLUKA05-PRE-LIB | Abstract | D00260 PCX86 00 | FLUKA05 Multi-Group, Multi-Purpose Nuclear Data Library, Neutrons, Photons, Charged Particles. |
| FSXJ32 | Abstract | D00244 MNYCP 00 | A Continuous Energy Cross Section MCNP Nuclear Data Library Based on JENDL-3.2. |
| GAKER-KIRA | Abstract | C00813 C3600 00 | Energy Transfer of Protons in H2O or Polyethylene and Deuterons in D2O. |
| GENP-2 | Abstract | C00575 ALLMF 00 | Generalized Perturbation Theory Code System. |
| MATXSLIBJ33 | Abstract | D00258 MNYCP 01 | JENDL-3.3 Based, 175 Neutron-42 Photon Groups (VITAMIN-J) MATXS Library for Discrete Ordinates Multi-Group Transport Codes. |
MCNP-DSP-EXE
810 | Abstract | C00699 MNYCP 01 | Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A. |
| MCRAC | Abstract | C00562 IBMPC 00 | Multiple Cycle Reactor Analysis Code. |
| MTR_PC 2.6 | Abstract | C00674 PC386 00 | Modular Code System for Neutronics, Thermalhydraulics and Shielding Calculations. |
| MVP-GMVP II | Abstract | C00739 MNYCP 00 | General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods. |
| PIXE2010 | Abstract | D00246 MNYCP 00 | Proton/alpha Ionization (K, L, M shell), Tabulated Cross Section Library. |
| PRECO2006 | Abstract | P00226 MNYCP 02 | Exciton Model Code System for Calculating Preequilibrium and Direct Double Differential Cross Sections. |
| RHEIN | Abstract | C00585 I3090 00 | Reactor Code System for Neutron Physics Calculation. |
| RMET21 | Abstract | C00597 D0VAX 00 | Detailed Space and Energy Treatment of Neutron Resonances for Homogeneous Mixtures and Cylinderized Reactor Cells. |
| TART2022 | Abstract | C00638 MNYCP 09 | Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System. |
TRIPOLI-4 8.1
OECD | Abstract | C00806 MNYCP 00 | Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport Calculations. |
TRIPOLI-4 9S
OECD | Abstract | C00815 MNYCP 00 | Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport Calculations. |
| VITENDF70.BOLIB | Abstract | D00261 PCX86 00 | ENDF/B-VII.0 Multi-Group Coupled (199n +42gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications. |
| VITJEF22.BOLIB | Abstract | D00241 MNYCP 00 | JEF-2.2 Multigroup Coupled (199n + 42?) Cross-Section Library in AMPX Format for Nuclear Fission Applications. |
| VITJEFF311.BOLIB | Abstract | D00257 MNYCP 01 | JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Section Library in AMPX Format for Nuclear Fission Applications. |
| WIMS-ANL 4.0 | Abstract | C00698 MNYCP 00 | Deterministic Code System for Reactor Lattice Calculation. |
| WIMSD-5B.12 | Abstract | C00656 MNYCP 02 | Deterministic Code System for Reactor Lattice Calculation |
| XSUN-2013 | Abstract | C00825 PCX86 00 | Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D |