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ISSN : 1738-1894(Print)
ISSN : 2288-5471(Online)
ISSN : 2288-5471(Online)
경수로 사용후핵연료 저장조 열부하 평가를 위한 연소조건 인자 민감도 분석
Sensitivity Analysis of Depletion Parameters for Heat Load Evaluation of PWR Spent Fuel Storage Pool
Abstract
As necessity of safety re-evaluation for spent fuel storage facility has emphasized after the Fukushima accident, accuracy improvement of heat load evaluation has become more important to acquire reliable thermal-hydraulic evaluation results. As groundwork, parametric and sensitivity analyses of various storage conditions for Kori Unit 4 spent fuel storage pool and spent fuel depletion parameters such as axial burnup effect, operation history, and specific heat are conducted using ORIGEN2 code. According to heat load evaluation and parametric sensitivity analyses, decay heat of last discharged fuel comprises maximum 80.42% of total heat load of storage facility and there is a negative correlation between effect of depletion parameters and cooling period. It is determined that specific heat is most influential parameter and operation history is secondly influential parameter. And decay heat of just discharged fuel is varied from 0.34 to 1.66 times of average value and decay heat of 1 year cooled fuel is varied from 0.55 to 1.37 times of average value in accordance with change of specific power. Namely depletion parameters can cause large variation in decay heat calculation of short-term cooled fuel. Therefore application of real operation data instead of user selection value is needed to improve evaluation accuracy. It is expected that these results could be used to improve accuracy of heat load assessment and evaluate uncertainty of calculated heat load.
사용후핵연료, 사용후핵연료 저장시설, 붕괴열, 열부하, 연소조건 인자, 저장 시나리오, Spent nuclear fuel, Spent nuclear fuel storage facility, Decay Heat, Heat load, Depletion parameter, Storage Scenario
Reference
JNFCWT
Online Submission
Korean Radioactive
Waste Society (KRS)
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