Postanalysis of the CNPS (Compact Nuclear Power Source) Critical Experiment

Conference · Sun Sep 18 00:00:00 EDT 1988

OSTI ID:6845835

Palmer, R. G. ^[1]

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1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

The Compact Nuclear Power Source (CNPS) was designed to produce electric power for remote sites where fuel logistics and costs would justify a remotely sited nuclear power plant. Since the reactor was of novel design with no appropriate benchmarks, a series of critical experiments was carried out at LANL. This paper describes the methodology and reports the results of the postanalysis that was performed on the critical experiments, which included several distinct critical configurations, the measurement of the isothermal temperature coefficient of reactivity and various material worths. Comparisons with measurements indicate that current methods and cross sections are adequate for calculating at least the beginning of life conditions in low enriched ²³⁵U-graphite cores.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6845835
• Report Number(s): LA-UR-88-2258; CONF-880911-11; ON: DE88014322
• Resource Relation: Conference: International Reactor Physics Conference, Jackson Hole, WY (United States), 18-21 Sep 1988; Other Information: Paper copy only, copy does not permit microfiche production
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
NUCLEAR POWER PLANTS
TESTING
BENCHMARKS
CALCULATION METHODS
DESIGN
FUEL ASSEMBLIES
FUEL RODS
GRAPHITE
PORTABLE SOURCES
REACTIVITY COEFFICIENTS
CARBON
ELEMENTAL MINERALS
ELEMENTS
FUEL ELEMENTS
MINERALS
NONMETALS
NUCLEAR FACILITIES
POWER PLANTS
RADIATION SOURCES
REACTOR COMPONENTS
THERMAL POWER PLANTS
Nuclear Criticality Safety Program (NCSP)
Critical Experiments
Postanalysis
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors