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: SELF SHIELDING
Package Name	Abstract	RSICC Tapelist	Title
BOREHOLE-EB6.8-MG	Abstract	D00268 MNYCP 00	Multi-Group Cross-Section Library for Deterministic and Monte Carlo Codes.
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.
ELAN	Abstract	P00141 ICL00 00	Neutron Cross-Section Self-Shielding Code System.
GECINX	Abstract	P00193 H6000 00	A Code System for Collapsing Multigroup Cross Sections in CCCC Format.
MIGROS3	Abstract	P00265 I0370 00	A Code for the Generation of Group Constants for Reactor Calculations from Neutron Nuclear Data in KEDAK Format.
NASIF-NARES	Abstract	P00121 I0360 00	A Code System for Computing Shielding Factors from ENDF/B Tapes.
REX2-87	Abstract	P00290 D8810 00	A Code For Calculating Self-Shielded Multigroup Neutron Cross Sections and Self-Shielding Factors From Preprocessed ENDF/B Basic Data Files.
ROLAIDS-CPM	Abstract	P00353 SUN04 00	Code System to Calculate Group-Averaged Cross Sections Using the Collision Probability Method.
SCOPE	Abstract	P00210 I3033 00	Computer Code System for Shipping Cask Optimization and Parametric Evaluation.
SELFS-3	Abstract	P00551 C6600 00	Self-Shielding Correlation of Foil Activation Neutron Spectra Analysis by SAND-II.
TRANSX 2.15	Abstract	P00317 MFMWS 01	Code system to produce neutron, photon, and particle transport tables for discrete-ordinates and diffusion codes from cross sections in MATXS format.
TRANSX-CTR	Abstract	P00206 CY000 00	Interfaces MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis.

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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.