Monte Carlo Cross-Section Testing for Fast 235U/238U criticals: ENDF/B-V versus ENDF/B-VI
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5874522
- 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 Lab., Schenectady, NY (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5874522
- Report Number(s):
- CONF-930601--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 68
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
663610* -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
ACTINIDE ISO
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CALCULATION METHODS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ENDF/B-V
ENDF/B-VI
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HEAVY NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MINUTES LIVING RADIOISOTOPES
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUCLEI
Nuclear Criticality Safety Program (NCSP)
POWER PLANTS
PROGRAMMING
R CODES
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
Results Comparision
SIMULATION
SPONTANEOUS FISSION RADIOISOTOPES
THERMAL POWER PLANTS
URANIUM 235
URANIUM 238
URANIUM ISOTOPES
VECTOR PROCESSING
YEARS LIVING RADIOISOTOPES
Zero-Power Reactor (ZPR)
220100 -- Nuclear Reactor Technology-- Theory & Calculation
663610* -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
ACTINIDE ISO
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CALCULATION METHODS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ENDF/B-V
ENDF/B-VI
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HEAVY NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MINUTES LIVING RADIOISOTOPES
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUCLEI
Nuclear Criticality Safety Program (NCSP)
POWER PLANTS
PROGRAMMING
R CODES
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
Results Comparision
SIMULATION
SPONTANEOUS FISSION RADIOISOTOPES
THERMAL POWER PLANTS
URANIUM 235
URANIUM 238
URANIUM ISOTOPES
VECTOR PROCESSING
YEARS LIVING RADIOISOTOPES
Zero-Power Reactor (ZPR)