Application of the LEPRICON unfolding procedure to the Arkansas Nuclear One-Unit 1 Reactor

Journal Article · Sun Jun 01 04:00:00 EDT 1986 · Nucl. Sci. Eng.; (United States)

OSTI ID:5343903

Maerker, R E; Broadhead, B L; Worley, B A; Williams, M L; Wagschal, J J

The development and demonstration of a new unfolding procedure involving pressure vessel surveillance dosimetry in pressurized water reactors are described. The complete methodology is contained in the LEPRICON code system, and provides techniques for calculating pressure vessel fluences and then adjusting them, with reduced uncertainties, on the basis of surveillance dosimetry measurements and a benchmark data base. An application of these techniques to an existing on-line commercial reactor is presented. Results indicate that the best estimate of the pressure vessel lifetime based on a limiting fluence above 1 MeV of 2 x 10/sup 19/ n/cm/sup 2/ is approx. =129+.11 effective full-power years, whereas the unadjusted estimate has an uncertainty twice as large.

• Research Organization: Oak Ridge National Lab., P.O. Box X, Oak Ridge, TN 37831
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5343903
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 93:2; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ARKANSAS-1 REACTOR
COMPUTER CODES
CONTAINERS
DATA BASE MANAGEMENT
DATA COVARIANCES
DOSIMETRY
ENERGY RANGE
ENRICHED URANIUM REACTORS
L CODES
MANAGEMENT
MEV RANGE
MEV RANGE 01-10
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
SERVICE LIFE
WATER COOLED REACTORS
WATER MODERATED REACTORS