An in-pile testing program to study the performance characteristics of coated particle fuels
Conference
·
· AIP Conference Proceedings (American Institute of Physics); (United States)
- Sandia National Laboratories, P.O. Box 5800, Albuquerque, New Mexico 87185 (United States)
Sandia National Laboratories is actively involved in testing coated particle nuclear fuels for the Space Nuclear Thermal Propulsion (SNTP) program managed by Phillips Laboratory. The testing program integrates the results of numerous in-pile and out-of-pile tests with modeling efforts to qualify fuel and fuel elements for the SNTP program. This paper briefly describes the capabilities of the Annular Core Research Reactor (in which the experiments are performed), the major in-pile tests, and the models used to determine the performance characteristics of the fuel and fuel elements.
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6801792
- Report Number(s):
- CONF-930103-; CODEN: APCPCS
- Journal Information:
- AIP Conference Proceedings (American Institute of Physics); (United States), Vol. 271:2; Conference: 10. symposium on space nuclear power and propulsion, Albuquerque, NM (United States), 10-14 Jan 1993; ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COATED FUEL PARTICLES
PERFORMANCE TESTING
SPACE PROPULSION REACTORS
TRIGA TYPE REACTORS
COMPUTER CODES
COOLANT LOOPS
FAILURES
FISSION PRODUCT RELEASE
POST-IRRADIATION EXAMINATION
SAFETY ANALYSIS
COOLING SYSTEMS
ENRICHED URANIUM REACTORS
FUEL PARTICLES
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
MOBILE REACTORS
POWER REACTORS
PROPULSION REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
SPACE POWER REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
NESDPS Office of Nuclear Energy Space and Defense Power Systems
210600* - Power Reactors
Auxiliary
Mobile Package
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220300 - Nuclear Reactor Technology- Fuel Elements
220600 - Nuclear Reactor Technology- Research
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22 GENERAL STUDIES OF NUCLEAR REACTORS
COATED FUEL PARTICLES
PERFORMANCE TESTING
SPACE PROPULSION REACTORS
TRIGA TYPE REACTORS
COMPUTER CODES
COOLANT LOOPS
FAILURES
FISSION PRODUCT RELEASE
POST-IRRADIATION EXAMINATION
SAFETY ANALYSIS
COOLING SYSTEMS
ENRICHED URANIUM REACTORS
FUEL PARTICLES
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
MOBILE REACTORS
POWER REACTORS
PROPULSION REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
SPACE POWER REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
NESDPS Office of Nuclear Energy Space and Defense Power Systems
210600* - Power Reactors
Auxiliary
Mobile Package
& Transportable
220300 - Nuclear Reactor Technology- Fuel Elements
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors