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자료유형
학술저널
저자정보
이은기 (한국수력원자력(주)한수원중앙연구원)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제3호
발행연도
2021.3
수록면
901 - 910 (10page)
DOI
https://doi.org/10.1016/j.net.2020.07.033

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KHNP recently has obtained the approval for the commercialization of the modified 37-element (or37 M) fuel bundle and now is loading the 37 M fuel bundles in CANDU-6 reactors in KOREA. One of themain issues for approval was the burnup limit. Due to CANDU design and neutronic characteristics, therewas no specific burnup restriction of a fuel bundle. The absence of a burnup limit does not mean that afuel bundle can stay in the CANDU reactor without a time limit. However, the regulator requestedtraditional design values as well as the burnup limit reflecting the computer code uncertainty. Themethod for the PWR burnup limit was not applied to the CANDU fuel bundle. Since there was noapproved methodology to build the burnup limit with uncertainties, KHNP introduced a Monte-Carlomethod coupled with a 95/95 approach to determine the conservative burnup limit from the viewpoint of the centerline temperature, internal pressure, strain measurement deviation. Moreover, toconsider the uncertainties of various computing models, a converted power uncertainty was introduced. This paper presents the methodology and puts forward the limits on burnup, evaluated for each of theexisting and modified fuel bundles, in consideration of the pressure tube aging condition.

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