Sensitivity of the sup 252 Cf-source-driven noise analysis method to fission content of spent LWR fuel
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7145788
- Oak Ridge National Lab., TN (United States)
- Univ. of Tennessee, Knoxville (United States)
The {sup 252}Cf-source-driven noise analysis method has been suggested as a method of measuring the subcriticality of spent light water reactor (LWR) fuel. A measurement of the subcritical neutron multiplication factor provides the parameter most directly related to criticality safety and can be used to verify the criticality safety margins of spent LWR fuel configurations. Previous measurements by this method have shown large changes in measured coherences for small changes in fissile mass. To explore this systematically, this paper evaluates the sensitivity of these noise analysis measurements to the amount of fission products in spent LWR fuel. This is of interest for validating calculations for burnup credit.
- OSTI ID:
- 7145788
- Report Number(s):
- CONF-920606--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
ACTINIDE ISO
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BORON
BURNUP
BWR TYPE REACTORS
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
COMPUTER CODES
CROSS SECTIONS
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FISSION PRODUCTS
FUELS
HEAVY NUCLEI
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HELIUM ISOTOPES
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPE ENRICHED MATERIALS
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K CODES
LIGHT NUCLEI
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MEASURING METHODS
METALS
MINUTES LIVING RADIOISOTOPES
MULTIGROUP THEORY
NEUTRON SOURCES
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
NUCLEAR FUELS
NUCLEI
PARTICLE SOURCES
POWER REACTORS
PWR TYPE REACTORS
RADIATION SOURCES
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR MATERIALS
REACTORS
SAFETY
SEMIMETALS
SLIGHTLY ENRICHED URANIUM
SPENT FUEL STORAGE
SPENT FUELS
SPONTANEOUS FISSION RADIOISOTOPES
STABLE ISOTOPES
STORAGE
SUBCRITICALITY
TESTING
THERMAL REACTORS
TRANSPORT THEORY
URANIUM
URANIUM 235
URANIUM ISOTOPES
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
ACTINIDE ISO
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BORON
BURNUP
BWR TYPE REACTORS
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
COMPUTER CODES
CROSS SECTIONS
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FISSION PRODUCTS
FUELS
HEAVY NUCLEI
HELIUM 3
HELIUM ISOTOPES
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPE ENRICHED MATERIALS
ISOTOPES
K CODES
LIGHT NUCLEI
MATERIALS
MEASURING METHODS
METALS
MINUTES LIVING RADIOISOTOPES
MULTIGROUP THEORY
NEUTRON SOURCES
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
NUCLEAR FUELS
NUCLEI
PARTICLE SOURCES
POWER REACTORS
PWR TYPE REACTORS
RADIATION SOURCES
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR MATERIALS
REACTORS
SAFETY
SEMIMETALS
SLIGHTLY ENRICHED URANIUM
SPENT FUEL STORAGE
SPENT FUELS
SPONTANEOUS FISSION RADIOISOTOPES
STABLE ISOTOPES
STORAGE
SUBCRITICALITY
TESTING
THERMAL REACTORS
TRANSPORT THEORY
URANIUM
URANIUM 235
URANIUM ISOTOPES
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES