APPLICATION OF THE LEPRICON UNFOLDING PROCEDURE TO THE ARKANSAS NUCLEAR ONE-UNIT 1 REACTOR.

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

doi:10.13182/NSE86-A17665

APPLICATION OF THE LEPRICON UNFOLDING PROCEDURE TO THE ARKANSAS NUCLEAR ONE-UNIT 1 REACTOR.

R. E. Maerker^*, B. L. Broadhead, B. A. Worley, M. L. Williams, J. J. Wagschal

^*Corresponding author for this work

Research output: Contribution to journal › Article › peer-review

19 Scopus citations

Abstract

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 multiplied by 10**1**9 n/cm**2 is approx. 129 plus or minus 11 effective full-power years, whereas the unadjusted estimate has an uncertainty twice as large.

Original language	English
Pages (from-to)	137-170
Number of pages	34
Journal	Nuclear Science and Engineering
Volume	93
Issue number	2
DOIs	https://doi.org/10.13182/NSE86-A17665
State	Published - 1986
Externally published	Yes

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title = "APPLICATION OF THE LEPRICON UNFOLDING PROCEDURE TO THE ARKANSAS NUCLEAR ONE-UNIT 1 REACTOR.",

abstract = "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 multiplied by 10**1**9 n/cm**2 is approx. 129 plus or minus 11 effective full-power years, whereas the unadjusted estimate has an uncertainty twice as large.",

author = "Maerker, {R. E.} and Broadhead, {B. L.} and Worley, {B. A.} and Williams, {M. L.} and Wagschal, {J. J.}",

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AU - Williams, M. L.

AU - Wagschal, J. J.

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N2 - 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 multiplied by 10**1**9 n/cm**2 is approx. 129 plus or minus 11 effective full-power years, whereas the unadjusted estimate has an uncertainty twice as large.

AB - 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 multiplied by 10**1**9 n/cm**2 is approx. 129 plus or minus 11 effective full-power years, whereas the unadjusted estimate has an uncertainty twice as large.

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APPLICATION OF THE LEPRICON UNFOLDING PROCEDURE TO THE ARKANSAS NUCLEAR ONE-UNIT 1 REACTOR.

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