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
Miscellaneous Code Collection (No Fee)
Package NameAbstractRSICC TapelistTitle
ANL-BPBAbstractM00004 MNYCP 00Argonne National Laboratory Code Center: Benchmark Problem Book.
ENDF UTIL. CODESAbstractM00008 MNYCP 00ENDF Checking and Utility Codes.
GANAPOL-ABNTTAbstractM00011 MNYCP 00Analytical Benchmarks; Case Studies in Neutron Transport Theory.
HGSYSTEMAbstractM00021 MNYCP 00Atmospheric Dispersion for Ideal Gases and Hydrogen Fluoride (HF)
HIMACAbstractM00001 MNYCP 02Experimental Data of Neutron Yields from Thick Targets Bombarded by 100 to 800 MeV / Nucleon Heavy Ions.
HOTSPOT 3.0.2AbstractM00009 IBMPC 03Health Physics Code System for Evaluating Accidents Involving Radioactive Materials.
JDL-IMPORTANCEAbstractM00005 MNYCP 00Adjoint Function: Physical Basis of Variational & Perturbation Theory in Transport & Diffusion Problems.
JDL-REACTOR-KINAbstractM00006 MNYCP 00Nuclear Reactor Kinetics and Control.
JDL-THERMODYNAMAbstractM00007 MNYCP 00Thermodynamics: Frontiers and Foundations.
MMRWAbstractM00018 MNYCP 00Canadian and Early British Energy Reports on Nuclear Reactor Theory (1940-1946).
MMRW-BOOKSAbstractM00020 MNYCP 00MMRW-BOOKS: Legacy books on slowing down, thermalization, particle transport theory, random processes in reactors.
NCSP-DATAbstractM00002 MNYCP 01Nuclear Data in Support of the Nuclear Criticality Safety Program.
PMK2-VVER440-REPORTSAbstractM00012 MNYCP 00Results of the Experiments Performed in the PMK-2 Facility for VVER Safety Studies.
REACTORSHIELDING-NMSAbstractM00014 MNYCP 00REACTORSHIELDING-NMS, Reactor Shielding for Nuclear Engineers.
ROCKWELL-RSDMAbstractM00017 MNYCP 00Reactor Shielding Design Manual by Rockwell T. III.
STEX IIAbstractM00010 MNYCP 00International Steam Explosion Experimental Data Base.
SULSAAbstractM00015 MNYCP 00A Solution for the Neutron Spectrum Unfolding Problem Without Using Input Spectrum (Report Only).
VVER-BENCHMARKSAbstractM00003 MNYCP 00Collection of Neutronic VVER Reactor Benchmarks.
123ABCDEFGHIJKLMNOPQRSTUVWXYZ
FAQ | ORNL Home | DOE | Site Map | Security Notice
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.