Postanalysis of the CNPS (Compact Nuclear Power Source) Critical Experiment
Conference
·
OSTI ID:6845835
- 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
- Country of Publication:
- United States
- Language:
- English
Similar Records
Compact nuclear power source critical experiments and analysis
Critical Experiments in Support of the CNPS (Compact Nuclear Power Source) Program
Preliminary evaluation of the Compact Nuclear Power Source (CNPS) critical experiments as a VHTR physics benchmark
Journal Article
·
Tue Oct 31 23:00:00 EST 1989
· Nuclear Science and Engineering; (USA)
·
OSTI ID:7048411
Critical Experiments in Support of the CNPS (Compact Nuclear Power Source) Program
Conference
·
Sun Sep 18 00:00:00 EDT 1988
·
OSTI ID:6913395
Preliminary evaluation of the Compact Nuclear Power Source (CNPS) critical experiments as a VHTR physics benchmark
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:22039716
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BENCHMARKS
CALCULATION METHODS
CARBON
Critical Experiments
DESIGN
ELEMENTAL MINERALS
ELEMENTS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
GRAPHITE
MINERALS
NONMETALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
Nuclear Criticality Safety Program (NCSP)
PORTABLE SOURCES
POWER PLANTS
Postanalysis
RADIATION SOURCES
REACTIVITY COEFFICIENTS
REACTOR COMPONENTS
TESTING
THERMAL POWER PLANTS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BENCHMARKS
CALCULATION METHODS
CARBON
Critical Experiments
DESIGN
ELEMENTAL MINERALS
ELEMENTS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
GRAPHITE
MINERALS
NONMETALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
Nuclear Criticality Safety Program (NCSP)
PORTABLE SOURCES
POWER PLANTS
Postanalysis
RADIATION SOURCES
REACTIVITY COEFFICIENTS
REACTOR COMPONENTS
TESTING
THERMAL POWER PLANTS