Comparison of safety parameters and transient behavior of a generic 10 MW reactor with HEU and LEU fuels
Conference
·
OSTI ID:5641783
Key safety parameters are compared for equilibrium cores of the IAEA generic 10 MW reactor with HEU and LEU fuels. These parameters include kinetics parameters, reactivity feedback coefficients, control rod worths, power peaking factors, and shutdown margins. Reactivity insertion and loss-of-flow transients are compared. Results indicate that HEU and LEU cores will behave in a very similar manner.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5641783
- Report Number(s):
- CONF-8310176-5; ON: DE84003680
- Country of Publication:
- United States
- Language:
- English
Similar Records
Neutronic safety parameters and transient analyses for Poland's MARIA research reactor.
Neutronic safety parameters and transient analyses for potential LEU conversion of the Budapest Research Reactor.
Transient analyses for HEU and LEU designs of the FRM-II.
Conference
·
Mon Sep 27 00:00:00 EDT 1999
·
OSTI ID:750510
Neutronic safety parameters and transient analyses for potential LEU conversion of the Budapest Research Reactor.
Conference
·
Mon Sep 27 00:00:00 EDT 1999
·
OSTI ID:750513
Transient analyses for HEU and LEU designs of the FRM-II.
Conference
·
Wed Oct 14 00:00:00 EDT 1998
·
OSTI ID:11046
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDES
BURNUP
CONTROL ROD WORTHS
COST
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FEEDBACK
FUEL CYCLE
FUELS
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
KINETICS
LOSS OF FLOW
MATERIALS
METALS
NUCLEAR FUELS
PEAK LOAD
POWER DISTRIBUTION
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR KINETICS
REACTOR MATERIALS
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SHUTDOWNS
SLIGHTLY ENRICHED URANIUM
URANIUM
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDES
BURNUP
CONTROL ROD WORTHS
COST
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FEEDBACK
FUEL CYCLE
FUELS
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
KINETICS
LOSS OF FLOW
MATERIALS
METALS
NUCLEAR FUELS
PEAK LOAD
POWER DISTRIBUTION
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR KINETICS
REACTOR MATERIALS
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SHUTDOWNS
SLIGHTLY ENRICHED URANIUM
URANIUM