Benchmarking Study of the MCNP Code Against Cold Critical Experiments

Conference · Sun Jun 02 00:00:00 EDT 1991 · Transactions of the American Nuclear Society

OSTI ID:5778412

The purpose of this study was to benchmark the widely used Monte Carlo code MCNP against a set of cold critical experiments with a view to using the code as a means of independently verifying the performance of faster but less accurate Monte Carlo and deterministic codes. The experiments simulated consisted of both fast and thermal criticals as well as fuel in a variety of chemical forms. A standard set of benchmark cold critical experiments was modeled. These included the two fast experiments, GODIVA and JEZEBEL, the TRX metallic uranium thermal experiments, the Babcock and Wilcox oxide and mixed oxide experiments, and the Oak Ridge National Laboratory (ORNL) and Pacific Northwest Laboratory (PNL) nitrate solution experiments. The principal case studied was a small critical experiment that was performed with boiling water reactor bundles.

• Research Organization: General Electric Co., San Jose, CA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 5778412
• Report Number(s): CONF-910603-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society, Vol. 63; Conference: Annual meeting of the American Nuclear Society (ANS), Orlando, FL (United States), 2-6 Jun 1991; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
REACTOR PHYSICS
M CODES
ACCURACY
BATTELLE PACIFIC NORTHWEST LABORATORIES
BENCHMARKS
BORON
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
EIGENVALUES
EXPERIMENTAL DATA
FAST NEUTRONS
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
ORNL
PLUTONIUM 239
REACTOR CORES
THERMAL NEUTRONS
URANIUM 238
VALIDATION
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
DATA
ELEMENTARY PARTICLES
ELEMENTS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FERMIONS
HADRONS
HEAVY NUCLEI
INFORMATION
ISOTOPES
NATIONAL ORGANIZATIONS
NEUTRONS
NUCLEI
NUCLEONS
NUMERICAL DATA
PHYSICS
PLUTONIUM ISOTOPES
RADIOISOTOPES
REACTOR COMPONENTS
SEMIMETALS
SIMULATION
SPONTANEOUS FISSION RADIOISOTOPES
TESTING
URANIUM ISOTOPES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
YEARS LIVING RADIOISOTOPES
Nuclear Criticality Safety Program (NCSP)
Monte Carlo Code
MCNP
GODIVA
Benchmark Study
JEZEBEL
220100* - Nuclear Reactor Technology- Theory & Calculation