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: ACTINIDES
Package Name	Abstract	RSICC Tapelist	Title
BISON 1.5	Abstract	C00464 HM200 00	One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
BISON-C	Abstract	C00659 MNYWS 00	One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
CACA-2	Abstract	C00302 I0360 00	Heavy Isotope and Fission-Product Concentration Calculation Code System.
DYN3D/M2	Abstract	P00579 I3090 00	Reactivity Transients in Light H2O Reactors with Hexagonal Geometry.
FISPACT-II 5.0	Abstract	C00836 MNYCP 03	Inventory Simulation Platform for Nuclear Observables and Materials Science.
FISPIN	Abstract	C00413 ICL00 00	Nuclide Inventory Calculation System.
GROUPSTRUCTURES	Abstract	D00274 MNYCP 00	GROUPSTRUCTURES, VITAMIN-J, XMAS, ECCO-33, ECCO2000 Standard Group Structures
PREMOR	Abstract	C00369 I0360 00	A Point Reactor Exposure Code System for Survey Nuclear Analysis of Power Plant Performance.
PURSE	Abstract	C00338 C6600 00	A Plutonium Radiation Source Code System.
RADAC	Abstract	C00627 PC486 02	Code System for Calculating Radioactive Decay and Accumulation of Decayed Products Using Integer-Array Arithmetic for Precise Evaluation of the Bateman Equations.
RASPA	Abstract	C00352 C7600 00	A Code for the Calculation of Buildup and Decay of Fission Products and Actinides.
REFREP	Abstract	C00570 D8810 00	A Near-Field Model For A Spent Fuel Repository.
RICECCC	Abstract	C00348 I0360 00	A Reactor Nuclide Inventory Code for Calculating Actinides and Fission Products.
SANDOR	Abstract	C00364 C7600 00	Isotope Generation and Depletion Code Matrix Exponential Method.

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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.