Published 1993
| Version v1
Journal article
Monte Carlo cross-section testing for fast 235U/238U criticals: ENDF/B-V versus ENDF/B-VI
Description
The purpose of this study is to compare the results of using either the reference cross-section data set ENDF/B-V or ENDF/B-VI RACER vectorized Monte Carlo calculations on several fast critical experiments. Seven benchmark cores were chosen that span a range of 235U enrichments and neutron leakage fractions. These include Godiva, Flat-Top-25, Zero-Power Reactor (ZPR)-Ill 6F, Vera-1 B, ZPR-III 12, ZPR- III 12, and Zebra-2
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 68
- Journal Page Range
- p. 463-464.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) annual meeting.
- Dates
- 20-24 Jun 1993.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25024139
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CROSS SECTIONS; MONTE CARLO METHOD; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; NUCLEAR POWER PLANTS; R CODES; REACTOR CORES; URANIUM 235; URANIUM 238; VECTOR PROCESSING
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; COMPUTER CODES; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FACILITIES; NUCLEI; POWER PLANTS; PROGRAMMING; RADIATION TRANSPORT; RADIOISOTOPES; REACTOR COMPONENTS; SIMULATION; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL POWER PLANTS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-930601--.