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.

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: LWR
Package NameAbstractRSICC TapelistTitle
BOXERAbstractC00766 MNYWS 00Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations
BUGENDF70.BOLIBAbstractD00262 PCX86 00ENDF/B-VII.0 Broad-Group Coupled Cross Section Library for LWR Shielding & Pressure Vessel Dosimetry Applications.
BUGJEFF311.BOLIBAbstractD00254 MNYCP 01JEFF-3.1.1 Broad-Group Coupled Cross Section Library For LWR Shielding & Pressure Vessel Dosimetry Applications.
COBRA-ENAbstractP00507 MNYCP 01Thermal-Hydraulic Transient Analysis of Reactor Cores.
DOSE-SGTRAbstractC00624 IBMPC 00Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR.
DYN3D/M2AbstractP00579 I3090 00Reactivity Transients in Light H2O Reactors with Hexagonal Geometry.
FASTGRASSAbstractP00479 MNYCP 00Code System to Predict Fission Product Release in Ubase Fuels.
FEMAXI 6 VER.1AbstractP00536 IBMPC 00Code System for Light Water Reactor Fuel Analysis.
FRAPCON2AbstractP00517 MFMWS 00Fuel Rod Thermal-Mechanical Behavior.
GRASS-SSTAbstractP00489 MNYCP 00Code System to Predict Fission-Gas Release & Fuel Swelling.
JASMINE V.3AbstractC00795 MNYCP 00JAEA Simulator for Multiphase INteractions and Explosions.
KICHE 1.3AbstractC00796 PCX86 00Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions.
KIMAbstractC00376 I3033 00A Two-Dimensional Monte Carlo Code System for Linear Neutron Transport Calculations.
MINETAbstractP00490 CY000 00Momentum Integral Network Method for Thermal-Hydraulic Systems Analysis.
MOSRA-LIGHTAbstractP00505 MNYWS 00High-Speed Three-Dimensional Nodal Diffusion Code System.
MURLIAbstractC00378 DP011 00Integral Transport Theory Code System for Thermal Reactor Lattice Cell Calculation.
NAUA-MOD5 NAUA-MOD5/MAbstractP00556 MNYCP 00Aerosols in Reactor Containment During Meltdown.
NEACRP-H2O-LATTICESAbstractD00265 MNYCP 00Compilation of Reactor Physics Measurements in LWRs Lattices.
NORMAAbstractP00471 PC586 00Code System to Solve Burnup Dependent Neutron Diffusion Equations in Two and Three Dimensions.
NORMA-FPAbstractP00470 PC586 00Code System to Perform Neutronic and Thermal-Hydraulic Subchannel Analysis from Converged Coarse-Mesh Nodal Solutions.
OMCOSTAbstractP00381 I3033 00Code System for Non-fuel O & M Cost Estimation for Large Steam-Electric Power Plants.
ORCENT-2AbstractP00474 I3033 00Code System for Analysis of Steam Turbine Cycles Supplied by Light Water Reactors.
ORLIBJ32AbstractD00255 MNYCP 00ORIGEN2 Libraries Based on JENDL-3.2.
OZMAAbstractC00406 I0370 00Calculation of Resonance Reaction Rates in Reactor Lattices Using Resonance Profile Tabulations.
PRESTAbstractC00355 I0360 00Calculator of Pressure and Temperature Transient in Containment Studies.
RAPIDAbstractC00797 PCX86 00RAdial Power and Burnup Prediction by Following Fissile Isotope Distribution in the Pellet.
SARA 4.16AbstractP00484 IBMPC 00System Analysis and Risk Assessment System.
SCRELAAbstractP00408 SUN05 00Code System for Supercritical Water Cooled Reactor LOCA Analysis.
THTAbstractC00480 I0360 00Three-Dimensional Neutron Coarse Mesh Code System to Evaluate Average Bundle Fluxes and Power in Light Water Reactors.
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.