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: ENDF/B FORMAT
Package Name	Abstract	RSICC Tapelist	Title
ACOH	Abstract	C00191 I3675 00	Aerojet COHORT Monte Carlo Code System.
BCG	Abstract	C00578 C0170 00	A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells.
BOXER	Abstract	C00766 MNYWS 00	Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations
ENDVER/GUI	Abstract	P00572 PCX86 00	The ENDF File Verification Support Package.
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.
ESP	Abstract	C00193 I0360 00	General Purpose Monte Carlo Neutron Transport Code System.
FISPIN	Abstract	C00413 ICL00 00	Nuclide Inventory Calculation System.
FOCUS	Abstract	C00390 I3033 00	Adjoint Monte Carlo Neutron Transport Code System.
O6R	Abstract	C00128 I3675 00	A General-Purpose Monte Carlo Transport Code System.
PADF-2007	Abstract	D00259 PCX86 00	Proton Activation Data File in ENDF-6 Format.
PALLAS-1D(VII)	Abstract	C00380 FM380 00	Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry.
PLOTENDF	Abstract	P00214 I3033 00	A Program for Producing Graphical Output.
PREPRO2019	Abstract	P00351 MNYCP 10	Pre-Processing Code System for Data in ENDF/B Format.
RMET21	Abstract	C00597 D0VAX 00	Detailed Space and Energy Treatment of Neutron Resonances for Homogeneous Mixtures and Cylinderized Reactor Cells.
SAM-CE	Abstract	C00187 C6600 00	Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations.
SAM-CE	Abstract	C00187 I0360 00	Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations.

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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.