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
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
- Resource Relation:
- Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC, USA, 30 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Application of LEPRICON methodology to the unfolding of neutron fluxes in the Arkansas Nuclear One-Unit 1 reactor
LEPRICON analysis of pressure vessel surveillance dosimetry inserted into H. B. Robinson-2 during cycle 9
Related Subjects
PRESSURE VESSELS
NEUTRON DOSIMETRY
BWR TYPE REACTORS
FLOWSHEETS
L CODES
LEAST SQUARE FIT
MATHEMATICAL MODELS
NEUTRON TRANSPORT
PWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
DIAGRAMS
DOSIMETRY
MAXIMUM-LIKELIHOOD FIT
NEUTRAL-PARTICLE TRANSPORT
NUMERICAL SOLUTION
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