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Khatib-Rahbar, M.*; Barrachin, M.*; Denning, R.*; Gabor, J.*; Gauntt, R.*; Herranz, L. E.*; Hobbins, R.*; Jacquemain, D.*; Maruyama, Yu; Metcalf, J.*; et al.
NUREG/CR-7282, ERI/NRC 21-204 (Internet), 160 Pages, 2021/04
Ishida, Shinya; Kawada, Kenichi; Fukano, Yoshitaka
Mechanical Engineering Journal (Internet), 7(3), p.19-00523_1 - 19-00523_17, 2020/06
The Phenomena Identification and Ranking Table (PIRT) approach was applied to the validation of SAS4A code in order to indicate the reliability of SAS4A code sufficiently and objectively. Based on this approach, issue and objective were clarified, plant design and scenario were defined, FOM and key phenomena were selected, and the code validation test matrix was completed with the results of investigation about analysis models and test cases. The results of the test analysis corresponding to this matrix show that the SAS4A models required for the IP evaluation were sufficiently validated. Furthermore, the validation with this matrix is highly reliable, since this matrix represents the comprehensive validation that also considers the relation between physical phenomena. In this study, the reliability and validity of SAS4A code were significantly enhanced by using PIRT approach to the sufficient level for CDA analyses in SFR.
Ishida, Shinya; Kawada, Kenichi; Fukano, Yoshitaka
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 10 Pages, 2019/05
Core Disruptive Accident (CDA) has been considered as one of the important safety issues in the severe accident evaluation of Sodium-cooled Fast Reactor (SFR), and SAS4A code is developed for Initiating Phase (IP) of CDA. Phenomena Identification and Ranking Table (PIRT) approach was applied to the validation of SAS4A code in order to enhance its reliability in this study. SAS4A was validated in the following steps: (1) selection of the figure of merit (FOM) corresponding to Unprotected Loss Of Flow (ULOF) which is one of the most important and typical events in CDA, (2) identification of the phenomena involved in ULOF, (3) ranking the important phenomena, (4) development of the code validation test matrix, and (5) test analyses for validation corresponding to the test matrix. The reliability and validity of SAS4A code were significantly enhanced by this validation with PIRT approach.
Tanaka, Masaaki
Dai-20-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.55 - 58, 2015/06
Numerical estimation method for high cycle thermal fatigue on a structure has been developed in JAEA. In development of numerical simulation codes and application of the codes to plant design, implementation of verification and validation (V&V) is indispensable. A procedure called as V2UP (Verification and Validation plus Uncertainty quantification and Prediction) has been made by referring to the existing guidelines on V&V. The PIRT (Phenomena Identification and Ranking Table) method based on the nine-step process used by the USNRC for the next generation nuclear plant development was employed at the first step of the V2UP. Through the first step of the V2UP with PIRT method, the conceptual model for the numerical estimation of high cycle thermal fatigue was successfully constructed.
Ohno, Shuji*; Miyahara, Shinya*; Kurata, Yuji
Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 6 Pages, 2004/00
no abstracts in English
Mascari, F.*; Nakamura, Hideo; De Rosa, F.*; D'Auria, F.*
no journal, ,
Amano, Yuki; Yamane, Yuichi; Muramatsu, Ken*; Fujiwara, Daisuke*; Kyo, Hisayuki*
no journal, ,
In recent years, PIRT (Phenomena Identification and Ranking Table) has been applied to quality improvement of safety analysis and review of safety analysis results in the US, etc. The PIRT is a table in which phenomena occurred in an event are identified and ranked by influence to figures-of-merit (FOMs). Nuclear fuel facilities severe accident research working group (SAWG) of Reprocessing and Recycle Technology Division in Atomic Energy Society of Japan has been developing the PIRT for boiling and drying out accident at fuel reprocessing plant to contribute to risk assessment of the fuel reprocessing plant, etc. Three presentations show the plan of this SAWG's activity and results of the activity. This presentation shows the outline of the activity, the purpose of the development of the PIRT, current condition of the development, etc. Development of the PIRT for boiling and drying out accident at fuel reprocessing plant is the world's first activity and certainly contributes technological development and technological inheritance in risk assessment and progress of application of risk assessment methodology of the fuel reprocessing plant in future.
