Application of surrogate models for statistical safety evaluation. Investigation of applicability to uncertainty analysis for PWRs
Creators
- 1. Institute of Nuclear Safety System, Inc., Institute of Nuclear Technology, Mihama, Fukui (Japan)
Description
Application of a surrogate model for statistical safety evaluation was discussed in the present paper on uncertainty analysis by the RELAP5 code for loss of coolant accidents in PWRs. Cross validation techniques were applied to verify the prediction capability of the surrogate model for the 95th percentile values of the safety evaluation parameters. Comparison with the RELAP5 uncertainty analysis results confirmed that the generalized performance of the surrogate model for the 95th percentile value prediction could be estimated using the cross validation on the training data set. From the results it was concluded that the surrogate model whose prediction accuracy for the 95th percentile values was confirmed by the cross validation could be used for the statistical safety evaluation. The effectiveness of the adaptive sampling technique was verified to improve the prediction accuracy for the 95th percentile values using a small number of training data. Comparison with the RELAP5 uncertainty analysis results confirmed that the prediction error of the 95th percentile values converged by repeating the adaptive sampling and the prediction errors were able to be estimated by the cross validation on the training data set. Therefore, the surrogate model with high accuracy for the 95th percentile value prediction was able to be effectively constructed by improving the surrogate model using the adaptive sampling procedure with the target of the 95th percentile values and confirming the model prediction accuracy using the cross validation on the training data set. (author)
Availability note (English)
Available from http://www.inss.co.jp/research/inss/journal28/Abstract (Japanese)
加圧水型原子炉の冷却材喪失事故を対象に,最適評価コードRELAP5による不確かさ解析に対して代替統計モデルを構築し,統計的安全評価における代替統計モデルの適用性を検討した.代替統計モデルによる95%累積確率値の計算精度を確認する方法として,交差検証法の適用性を検討した.RELAP5不確かさ解析との比較により,代替統計モデルが95%累積確率値を予測する汎化性能があることの判定は,学習データを用いた交差検証によって推定可能であることを確認した.したがって,交差検証を行い95%累積確率値の予測精度を確認した代替統計モデルを用いることにより,統計的安全評価が可能であると言える,少ないデータ数で効率的に95%累積確率値の予測精度のよいモデルを構築するために,適応的サンプリング法の有用性を検討した.RELAP5不確かさ解析との比較により,適応的サンプリングを繰り返すことにより,95%累積確率値の計算誤差が収束すること,および95%累積確率値の計算誤差は学習データに対する交差検証によって推定可能であることを確認した.以上より,95%累積確率値を目標値とした適応的サンプリングにより代替統計モデルを更新し,交差検証により計算精度を推定することによって,95%累積確率値の計算精度が高い代替統計モデルを効率的に構築することができると言える.(著者)Additional details
Additional titles
- Original title (Japanese)
- 統計的安全評価における代替統計モデルの適用.実機条件の不確かさ解析に対する適用性の検討
Identifiers
Publishing Information
- Journal Title
- INSS Journal
- Journal Volume
- 28
- Journal Page Range
- p. 151-162
- ISSN
- 1340-4482
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53096585
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Descriptors DEI
- CLADDING; DATA COVARIANCES; HEAT TRANSFER; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; R CODES; REGRESSION ANALYSIS; SAFETY ANALYSIS; SAMPLING; SBLOCA; STOCHASTIC PROCESSES; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DEPOSITION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; LOSS OF COOLANT; MATHEMATICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; STATISTICS; SURFACE COATING; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 20 refs., 11 figs., 3 tabs.