Accounting for changing source distributions in light water reactor surveillance dosimetry analysis
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6754906
A technique is described to account for effects of space- and time-dependent core source variations on pressure vessel surveillance dosimetry analysis. The procedure first defines an easily implemented geometry for a single adjoint transport calculation. The results from the adjoint calculation can then be combined with those from a single forward calculation, in conjunction with an adjoint scaling technique, to yield activities and pressure vessel fluxes simultaneously for a wide range of source distributions, dosimeter response functions, and detector locations. This method has been implemented in the LEPRICON code system for vessel fluence determination. An application to an R-theta model of an operating power reactor shows that effects of source perturbations resulting in 20% changes in the core leakage can be predicted within -- 3% at both downcomer and cavity dosimeter locations, for six different dosimeters, by choice of a single suitable adjoint response function.
- Research Organization:
- Oak Ridge National Lab., P.O. Box X, Oak Ridge, TN 37831
- OSTI ID:
- 6754906
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 94:4; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Wed Dec 31 23:00:00 EST 1986
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·
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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
COMPUTER CODES
CONTAINERS
COOLING SYSTEMS
DISTURBANCES
DOSEMETERS
DOSIMETRY
ENERGY SYSTEMS
FUNCTIONS
L CODES
LEAKS
MEASURING INSTRUMENTS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
RESPONSE FUNCTIONS
SPACE DEPENDENCE
SURVEILLANCE
TIME DEPENDENCE
TRANSPORT THEORY
WATER COOLED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTER CODES
CONTAINERS
COOLING SYSTEMS
DISTURBANCES
DOSEMETERS
DOSIMETRY
ENERGY SYSTEMS
FUNCTIONS
L CODES
LEAKS
MEASURING INSTRUMENTS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
RESPONSE FUNCTIONS
SPACE DEPENDENCE
SURVEILLANCE
TIME DEPENDENCE
TRANSPORT THEORY
WATER COOLED REACTORS