Monte Carlo Cross-Section Testing for Fast ²³⁵U/²³⁸U criticals: ENDF/B-V versus ENDF/B-VI

Conference · Sun Jun 20 00:00:00 EDT 1993 · Transactions of the American Nuclear Society

OSTI ID:5874522

Weinman, J. P. ^[1]

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1. Knolls Atomic Power Lab., Schenectady, NY (United States)

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.

• Research Organization: Knolls Atomic Power Laboratory (KAPL), Niskayuna, NY (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 5874522
• Report Number(s): CONF-930601-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society, Vol. 68; Conference: American Nuclear Society (ANS) Annual Meeting , San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
NEUTRON TRANSPORT
COMPUTERIZED SIMULATION
MONTE CARLO METHOD
URANIUM 235
NUCLEAR DATA COLLECTIONS
URANIUM 238
CROSS SECTIONS
NUCLEAR POWER PLANTS
R CODES
REACTOR CORES
VECTOR PROCESSING
ACTINIDE ISO
ACTINIDE ISOTOPES
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
Nuclear Criticality Safety Program (NCSP)
Results Comparision
Zero-Power Reactor (ZPR)
ENDF/B-V
ENDF/B-VI
663610* - Neutron Physics- (1992-)
220100 - Nuclear Reactor Technology- Theory & Calculation