Reduction of the sodium-void coefficient of reactivity by using a technetium layer
Conference
·
OSTI ID:10171782
Analyses were performed using the US Advanced Liquid Metal Reactor (ALMR) core design to determine the feasibility of using it as an {sup 99}Tc burner while reducing the sodium-void coefficient. A layer of {sup 99}Tc of variable thickness was inserted around the core midplane in Rows 2 through 5 and all blanket assemblies were replaced with fuel assemblies. The results indicate that a core with a 34-cm-thick layer in Rows 2 through 5 has the optimum characteristics of sodium-void coefficient, {sup 99}Tc destruction rate, and fuel enrichment.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 10171782
- Report Number(s):
- WHC-SA-1793; CONF-9309151-5; ON: DE93016827; TRN: 93:017851
- Resource Relation:
- Conference: Global `93: international conference and technology exhibition,Seattle, WA (United States),12-17 Sep 1993; Other Information: PBD: Jun 1993
- Country of Publication:
- United States
- Language:
- English
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PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD DECEMBER 24, 1959 TO FEBRUARY 23, 1960
Journal Article
·
Mon Aug 01 00:00:00 EDT 1994
· Nuclear Science and Engineering; (United States)
·
OSTI ID:10171782
Sodium void reactivity comparison for advanced liquid-metal reactor fuels
Conference
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Tue Jan 01 00:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:10171782
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PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD DECEMBER 24, 1959 TO FEBRUARY 23, 1960
Technical Report
·
Mon Oct 31 00:00:00 EST 1960
·
OSTI ID:10171782
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
LIQUID METAL COOLED REACTORS
VOID COEFFICIENT
NUCLEAR FUELS
COMPARATIVE EVALUATIONS
TECHNETIUM 99
REACTOR CORES
210500
220600
POWER REACTORS
BREEDING
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
LIQUID METAL COOLED REACTORS
VOID COEFFICIENT
NUCLEAR FUELS
COMPARATIVE EVALUATIONS
TECHNETIUM 99
REACTOR CORES
210500
220600
POWER REACTORS
BREEDING
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS