Online Catalog
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 Subject: BENCHMARKS
Package NameAbstractRSICC TapelistTitle
AIRFEWGAbstractD00049 I0360 00Results of ANISN Multigroup Calculations of Gamma-Ray, Neutron, and Secondary Gamma-Ray Transport in Infinite Homogeneous Air Using DLC-31/(DPL-1/FEWG1) Cross Sections.
ANL-BPBAbstractM00004 MNYCP 00Argonne National Laboratory Code Center: Benchmark Problem Book.
BPAbstractD00008 I0360 00Data for Selected Shielding Benchmark Problems Specified in ORNL-RSIC-25, Shielding Benchmark Problems.
BRMSTKAbstractP00044 C6600 00CSEWG Integral Data Testing Shielding Experiment Code System.
BRMSTKAbstractP00044 I3691 00CSEWG Integral Data Testing Shielding Experiment Code System.
EURLIB-IIIAbstractD00035 I0360 01100 Neutron, 20 Gamma-Ray Group Cross Section Library for Use in the European Shielding Benchmark Program.
GANAPOL-ABNTTAbstractM00011 MNYCP 00Analytical Benchmarks; Case Studies in Neutron Transport Theory.
MOSRA-LIGHTAbstractP00505 MNYWS 00High-Speed Three-Dimensional Nodal Diffusion Code System.
SINBAD SEARCH TOOLAbstractP00580 MNYCP 00SINBAD Search Tool
SINBAD-2022AbstractD00237 MNYCP 06Shielding Integral Benchmark Archive and Database.
SRAC95AbstractC00716 MNYWS 00Thermal Reactor Code System for Reactor Design and Analysis.
SWATAbstractC00714 MNYCP 01Step-Wise Burnup Analysis Code System to Combine SRAC-95 Cell Calculation Code and ORIGEN2.
TRANSMITAbstractD00020 I0360 00Experimental Neutron Transmission Data Used to Test Total Cross Sections.
VVER-BENCHMARKSAbstractM00003 MNYCP 00Collection of Neutronic VVER Reactor Benchmarks.
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The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.