CSRL-V: processed ENDF/B-V 227-neutron-group and pointwise cross-section libraries for criticality safety, reactor, and shielding studies
A P/sub 3/ 227-neutron-group cross-section library has been processed for the subsequent generation of problem-dependent fine- or broad-group cross sections for a broad range of applications, including shipping cask calculations, general criticality safety analyses, and reactor core and shielding analyses. The energy group structure covers the range 10/sup -5/ eV - 20 MeV, including 79 thermal groups below 3 eV. The 129-material library includes processed data for all materials in the ENDF/B-V General Purpose File, several data sets prepared from LENDL data, hydrogen with water- and polyethyelene-bound thermal kernels, deuterium with C/sub 2/O-bound thermal kernels, carbon with a graphite thermal kernel, a special 1/V data set, and a dose factor data set. The library, which is in AMPX master format, is designated CSRL-V (Criticality Safety Reference Library based on ENDF/B-V data). Also included in CSRL-V is a pointwise total, fission, elastic scattering, and (n,..gamma..) cross-section library containing data sets for all ENDF/B-V resonance materials. Data in the pointwise library were processed with the infinite dilute approximation at a temperature of 296/sup 0/K.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5334128
- Report Number(s):
- NUREG/CR-2306; ORNL/CSD/TM-160; ON: DE82012768; TRN: 82-013328
- Resource Relation:
- Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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CSRL-V: an ENDF/B-V 227-Group Cross Section Library for Criticality Safety Studies
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Related Subjects
42 ENGINEERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CROSS SECTIONS
NUCLEAR DATA COLLECTIONS
REACTOR KINETICS
COMPUTER CALCULATIONS
REACTOR CORES
SHIELDING
SPENT FUEL CASKS
CASKS
CONTAINERS
KINETICS
REACTOR COMPONENTS
220100* - Nuclear Reactor Technology- Theory & Calculation
420203 - Engineering- Handling Equipment & Procedures
420205 - Engineering- Transport & Storage Facilities- (1980-)
652020 - Nuclear Properties & Reactions
A=220 & above
Experimental