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: FISSION PRODUCTS
Package Name	Abstract	RSICC Tapelist	Title
AARE-V1.0	Abstract	C00846 MNYCP 00	Activation in Accelerator Radiation Environments
ACAB-2008	Abstract	C00758 MNYCP 01	Activation Abacus Inventory Code System for Nuclear Applications.
ADENA	Abstract	P00190 C0000 00	Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra.
ADENA	Abstract	P00190 I3033 00	Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra.
ALARA 2.7.8	Abstract	C00723 MNYCP 00	Code System for Analytic and Laplacian Adaptive Radioactivity Analysis.
DASH-FP	Abstract	C00366 C0000 00	A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products.
EPRI-CINDER	Abstract	C00309 C6600 00	General Point-Depletion and Fission Product Code System and Four-Group Fission Product Neutron Absorption Chain Data Library Generated from ENDF/B-IV for Thermal Reactors.
FDKR	Abstract	C00541 I4381 00	Radioactivity and Dose Rate Calculation Code for Fission, Fusion and Hybrid Reactors.
FIPDIG	Abstract	C00251 I0360 00	One-Dimensional Time-Dependent Fission Product Diffusion Code System.
FISP-6	Abstract	C00538 I3090 00	An Enhanced Code for the Evaluation of Fission Product Inventories and Decay Heat.
FISPIN	Abstract	C00413 ICL00 00	Nuclide Inventory Calculation System.
FISSP & CLOUD	Abstract	C00163 MNYCP 01	Fission Product Inventory, Release, Transport and Dose Calculation.
FONTA	Abstract	C00423 S4044 00	Code System For Calculating Individual And Collective Doses From Reactor Accidents Using Pasquill's Plume Model.
FPGAM	Abstract	C00386 F2307 00	Calculation of Fission-Product Gamma-Ray Spectra.
FPIC	Abstract	C00028 I3675 00	Fission Product Inventory Code.
FRCRL2	Abstract	C00231 C6400 00	Calculation of Fission-Product Release in Reactor Accident Analyses.
GRASS-SST	Abstract	P00489 MNYCP 00	Code System to Predict Fission-Gas Release & Fuel Swelling.
HEATKAU	Abstract	C00805 PCX86 00	HEATKAU Program.
HORN	Abstract	C00568 I3083 00	A Computer Code To Analyze The Gas-Phase Transport of Fission Products In Reactor Cooling System Under Severe Accidents.
LASER	Abstract	C00344 I0360 00	A One-Dimensional, Neutron-Thermalization, Lattice-Cell Program Based on MUFT and THERMOS.
LEAF	Abstract	C00312 C6600 00	Fission Product Release Calculator-From a Reactor Containment Building for Arbitrary Radioactive Decay Chains.
MARMER	Abstract	C00579 D8350 00	A Flexible Point-Kernel Shielding Code System.
MARMER	Abstract	C00579 PC486 00	A Flexible Point-Kernel Shielding Code System.
PADLOC	Abstract	C00330 U0000 00	A One-Dimensional, Time-Dependent Program for Calculating Coolant and Plateout Fission Product Concentrations in a Network of Pipes.
PROCIV	Abstract	C00488 U1110 00	A Code System for Calculating the Protection Factors Against Radioactive Fallout for Apartment Buildings.
RACER	Abstract	C00174 U1108 00	Calculation of Potential External Dose from Airborne Fission Products Following Postulated Reactor Accident.
RAD 2	Abstract	C00122 I7090 00	Fission Product Radioactivities Calculation.
RRR	Abstract	C00196 I0360 00	Radiation Transport in Air-Analysis of Routine Releases of Short-Lived Radioactive Nuclides.
RSAC-7.2	Abstract	C00761 PC586 01	Radiological Safety Analysis.
SFACTOR	Abstract	C00310 I0360 00	Dose Equivalent to a Target Organ Calculator.
SLIDERULE 1.0	Abstract	C00704 PC586 01	Nuclear Criticality Slide Rule.
SPIRT-NRC USSO	Abstract	P00198 I3033 01	Computerized Mathematical Models of Spray Washout of Airborne Contaminants (Radioactivity) in Containment Vessels.
SUBDOSA-II	Abstract	C00270 U1100 00	Calculation of External Gamma-Ray and Beta-Ray Doses from Accidental Atmospheric Releases of Radionuclides.
TACT-III	Abstract	C00447 I3033 00	Calculation of the Transport of Radioactivity from a Reactor Core.
WIMS-ANL 4.0	Abstract	C00698 MNYCP 00	Deterministic Code System for Reactor Lattice Calculation.

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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.