The LEPRICON (Least-Squares Electric Power Research Institute Consolidation) code system: Consolidation of transport analytical and unfolding procedures in LWR (Light Water Reactor) pressure vessel dosimetry
Conference
·
OSTI ID:6810632
The LEPRICON (for Least-Square Electric Power Research Institute Consolidation program) code system has been developed over the past ten years to provide a complete analysis of Light Water Reactor (LWR) pressure vessel dosimetry. The system incorporated nine modules. All but one of the modules treat various aspects of neutron transport from the core through the reactor internals to dosimetry locations in the downcomer and/or reactor cavity regions and to critical fluence locations in the pressure vessel. The LEPRICON adjustment module, on the other hand, performs a state-of-the-art least-squares analysis of the results from the transport modules, a procedure often referred as spectral unfolding or the combining of integral and differential data. In terms of development, the adjustment module alone required about 70 percent of the total effort, for reasons that soon will become apparent. The results from the LEPRICON system thus represent prior and adjusted fluences in each of 38 groups from 0.1 to 20 MeV, along with their corresponding standard deviations, at critical locations on the pressure vessel. 7 refs., 1 fig.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6810632
- Report Number(s):
- CONF-881011-2; ON: DE88011403
- Country of Publication:
- United States
- Language:
- English
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The LEPRICON code system: Consolidation of transport analytical and unfolding procedures in LWR pressure vessel dosimetry
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· Transactions of the American Nuclear Society; (USA)
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OSTI ID:5434202
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·
OSTI ID:6498987
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·
Fri Aug 01 00:00:00 EDT 1986
·
OSTI ID:5156736
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
BWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
DIAGRAMS
DOSIMETRY
FLOWSHEETS
L CODES
LEAST SQUARE FIT
MATHEMATICAL MODELS
MAXIMUM-LIKELIHOOD FIT
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DOSIMETRY
NEUTRON TRANSPORT
NUMERICAL SOLUTION
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION TRANSPORT
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
DIAGRAMS
DOSIMETRY
FLOWSHEETS
L CODES
LEAST SQUARE FIT
MATHEMATICAL MODELS
MAXIMUM-LIKELIHOOD FIT
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DOSIMETRY
NEUTRON TRANSPORT
NUMERICAL SOLUTION
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION TRANSPORT
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS