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: GAMMA-RAY CROSS SECTION PROCESSING
Package Name	Abstract	RSICC Tapelist	Title
AMPX-77	Abstract	P00315 ALLMF 01	Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B.
AXMIX-PC	Abstract	P00297 IBMPC 00	ANISN Cross Section Code System.
DATINIT	Abstract	P00258 DGMV1 00	Interactive Program To Access Photon Interaction Data.
DINT	Abstract	P00049 C6600 00	Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations.
DINT	Abstract	P00049 I0360 00	Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations.
ENBAL2	Abstract	P00160 I0370 00	A Program to Generate Multigroup Neutron Kerma Factors.
FOURACES	Abstract	P00183 I0370 00	Code System for Producing Spectrum Weighted, Group Averaged Cross Sections from ENDF/B, KEDAK, or UK Libraries.
GAMIDENT	Abstract	P00154 C0000 00	A Program to Aid in the Identification of Unknown Materials by Gamma-ray Spectroscopy.
GAMLEG-75	Abstract	P00086 C7600 00	Multigroup Cross Section Generator for Photon Transport Calculations.
HEITLER	Abstract	P00004 I7030 00	Cross Section Generator.
INFLTB	Abstract	P00313 ALLCP 00	Gamma-Ray Absorption Coefficient Calculation.
LIBMAK	Abstract	P00087 I0360 00	ANISN-Type Binary Data Processing Code System.
MICAP	Abstract	P00261 I3033 00	A Monte Carlo Code System for Analysis of Ionization Chamber Responses.
NJOY91.119	Abstract	P00171 MFMWS 04	Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY94.61	Abstract	P00355 MFMWS 03	Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY97.0	Abstract	P00368 MNYCP 00	Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY99.0	Abstract	P00480 MNYCP 00	Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY-UTIL-EIR	Abstract	P00296 C0825 00	Utilities For the NJOY (6/83) Nuclear Data Processing System.
SATURN	Abstract	P00057 I3675 00	P1 or Transport Corrected Multigroup Neutron Cross Section Data Processor.
STAPREF	Abstract	P00498 PC586 00	Code System to Calculate Nuclear Reaction Cross Sections by Evaporation Model.
STAPRE-H95	Abstract	P00325 MNYCP 01	Code System to Calculate Energy-Averaged Cross Sections of Particle Induced Nuclear Reactions.
TECALC	Abstract	P00074 DP010 00	Interactive Calculation of Compton Coherent and Photoelectric Mass Attenuation Coefficients for Photons (E<1 MeV), and the Mass Absorption Coefficient for Known Materials.

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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.