RSICC Catalog

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 Keyword: LWR
Package Name	Abstract	RSICC Tapelist	Title
BOXER	Abstract	C00766 MNYWS 00	Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations
BUGENDF70.BOLIB	Abstract	D00262 PCX86 00	ENDF/B-VII.0 Broad-Group Coupled Cross Section Library for LWR Shielding & Pressure Vessel Dosimetry Applications.
BUGJEFF311.BOLIB	Abstract	D00254 MNYCP 01	JEFF-3.1.1 Broad-Group Coupled Cross Section Library For LWR Shielding & Pressure Vessel Dosimetry Applications.
COBRA-EN	Abstract	P00507 MNYCP 01	Thermal-Hydraulic Transient Analysis of Reactor Cores.
DOSE-SGTR	Abstract	C00624 IBMPC 00	Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR.
DYN3D/M2	Abstract	P00579 I3090 00	Reactivity Transients in Light H2O Reactors with Hexagonal Geometry.
FASTGRASS	Abstract	P00479 MNYCP 00	Code System to Predict Fission Product Release in Ubase Fuels.
FEMAXI 6 VER.1	Abstract	P00536 IBMPC 00	Code System for Light Water Reactor Fuel Analysis.
FRAPCON2	Abstract	P00517 MFMWS 00	Fuel Rod Thermal-Mechanical Behavior.
GRASS-SST	Abstract	P00489 MNYCP 00	Code System to Predict Fission-Gas Release & Fuel Swelling.
JASMINE V.3	Abstract	C00795 MNYCP 00	JAEA Simulator for Multiphase INteractions and Explosions.
KICHE 1.3	Abstract	C00796 PCX86 00	Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions.
KIM	Abstract	C00376 I3033 00	A Two-Dimensional Monte Carlo Code System for Linear Neutron Transport Calculations.
MINET	Abstract	P00490 CY000 00	Momentum Integral Network Method for Thermal-Hydraulic Systems Analysis.
MOSRA-LIGHT	Abstract	P00505 MNYWS 00	High-Speed Three-Dimensional Nodal Diffusion Code System.
MURLI	Abstract	C00378 DP011 00	Integral Transport Theory Code System for Thermal Reactor Lattice Cell Calculation.
NAUA-MOD5 NAUA-MOD5/M	Abstract	P00556 MNYCP 00	Aerosols in Reactor Containment During Meltdown.
NEACRP-H2O-LATTICES	Abstract	D00265 MNYCP 00	Compilation of Reactor Physics Measurements in LWRs Lattices.
NORMA	Abstract	P00471 PC586 00	Code System to Solve Burnup Dependent Neutron Diffusion Equations in Two and Three Dimensions.
NORMA-FP	Abstract	P00470 PC586 00	Code System to Perform Neutronic and Thermal-Hydraulic Subchannel Analysis from Converged Coarse-Mesh Nodal Solutions.
OMCOST	Abstract	P00381 I3033 00	Code System for Non-fuel O & M Cost Estimation for Large Steam-Electric Power Plants.
ORCENT-2	Abstract	P00474 I3033 00	Code System for Analysis of Steam Turbine Cycles Supplied by Light Water Reactors.
ORLIBJ32	Abstract	D00255 MNYCP 00	ORIGEN2 Libraries Based on JENDL-3.2.
OZMA	Abstract	C00406 I0370 00	Calculation of Resonance Reaction Rates in Reactor Lattices Using Resonance Profile Tabulations.
PREST	Abstract	C00355 I0360 00	Calculator of Pressure and Temperature Transient in Containment Studies.
RAPID	Abstract	C00797 PCX86 00	RAdial Power and Burnup Prediction by Following Fissile Isotope Distribution in the Pellet.
SARA 4.16	Abstract	P00484 IBMPC 00	System Analysis and Risk Assessment System.
SCRELA	Abstract	P00408 SUN05 00	Code System for Supercritical Water Cooled Reactor LOCA Analysis.
THT	Abstract	C00480 I0360 00	Three-Dimensional Neutron Coarse Mesh Code System to Evaluate Average Bundle Fluxes and Power in Light Water Reactors.

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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.