Analysis of Safety-Related Physics Measurements in the Initial Gas-Cooled Fast Breeder Reactor Critical Experiment
Conference
·
OSTI ID:7347830
- General Atomics, San Diego, CA (United States)
Analyses of experiments in the initial critical assemblies for the gas-cooled fast breeder reactor (GCFR) were conducted using the calculational methods at General Atomic (GA) for GCFR design. The assemblies, constructed on the ZPR-9 facility at Argonne National Laboratory, simulated features of the 300-MW(e) GCFR demonstration reactor. Studies relating to the safety of this reactor design and to the GCFR concept in general were concerned with (1) reactivity coefficients of fuel and poison materials to evaluate loading and control requirements, (2) the worth of helium coolant in a depressurization event, (3) the Doppler effect in uranium to determine power coefficients, and (4) the effect of hypothesized steam ingress into coolant channels as a potential for reactivity addition and altering core neutronic and control characteristics. Results are reported for GA analyses of such safety-related physics measurements in two basic assemblies, the 3150-liter phase I core with a coolant void fraction of 55% and the 1300-liter phase II core with a 45% void fraction.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Energy Research and Development Administration (ERDA)
- OSTI ID:
- 7347830
- Report Number(s):
- GA-A-14090; CONF-761001-17
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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220900* -- Nuclear Reactor Technology-- Reactor Safety
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BREEDER REACTORS
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Calculated-To-Experimental Ratios (C/E Values)
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DEPRESSURIZATION
DOPPLER COEFFICIENT
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FAST REACTORS
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GCFR TYPE REACTORS
HELIUM COOLED REACTORS
KINETICS
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Nuclear Criticality Safety Program (NCSP)
REACTIVITY COEFFICIENTS
REACTOR KINETICS
REACTOR SAFETY
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SAFETY
STRUCTURAL MODELS
VOID FRACTION
ZERO POWER REACTORS
ZPR-9 REACTOR
Zero-Power Critical Facilities
210500 -- Power Reactors
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220900* -- Nuclear Reactor Technology-- Reactor Safety
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BREEDER REACTORS
Basic Neutronics
Calculated-To-Experimental Ratios (C/E Values)
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DEPRESSURIZATION
DOPPLER COEFFICIENT
Doppler Coefficient Analyses
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
Eigenvalue
Evaluated Nuclear Data File (ENDF)
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
KINETICS
Liquid Metal Cooled Fast Breeder Reactor (LMFBR) Assemblies
MOCKUP
Mixed Oxide Fuel Rods
Nuclear Criticality Safety Program (NCSP)
REACTIVITY COEFFICIENTS
REACTOR KINETICS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
STRUCTURAL MODELS
VOID FRACTION
ZERO POWER REACTORS
ZPR-9 REACTOR
Zero-Power Critical Facilities