Published February 1976
| Version v1
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LIB-IV, a library of group constants for nuclear reactor calculations
Description
A 50-group, 101-isotope library of multigroup constants for nuclear reactor design is described. Nuclear cross sections, self-shielding factors, transfer matrices, and delayed neutron data were generated with MINX and NJOY using evaluated data from ENDF/B-IV. The output is in the CCCC-III interface format. Test results are presented for six CSEWG benchmark critical assemblies
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS.
Files
Additional details
Additional titles
- Augmented title (English)
- 50-group, 101-isotope library generated with MINX from ENDF/B-IV
Publishing Information
- Imprint Pagination
- 27 p.
- Report number
- LA--6260-MS
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7274552
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- DELAYED NEUTRONS; GROUP CONSTANTS; MULTIGROUP THEORY; NEUTRON REACTIONS; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; REACTOR KINETICS; SELF-SHIELDING
- Descriptors DEC
- BARYON REACTIONS; BARYONS; CROSS SECTIONS; ELEMENTARY PARTICLES; FERMIONS; FISSION NEUTRONS; HADRON REACTIONS; HADRONS; KINETICS; NEUTRONS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUCLEONS; TRANSPORT THEORY
Optional Information
- Notes
- Available from NTIS. $4.00.