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Tanaka, Masaaki; Nakada, Kotaro*; Kudo, Yoshiro*
Nihon Kikai Gakkai-Shi, 123(1222), p.26 - 29, 2020/09
In the nuclear engineering, simulations are used in radiation, thermal hydraulic, chemical reaction, and structural fields, and the integrated fields thereof, to be applied to the design, construction and operation of nuclear facilities. This article describes brief history of discussion in the AESJ to the publication and introductory explanation of the procedures in the five major elements described in the "Guideline for Credibility Assessment of Nuclear Simulations (AESJ-SC-A008: 2015)". And also, a practical experience of the V&V activity according to the fundamental concept indicated in the Guideline is introduced.
Nakada, Kotaro*; Kudo, Yoshiro*; Koshizuka, Seiichi*; Tanaka, Masaaki
Nihon Genshiryoku Gakkai-Shi ATOMO
, 60(3), p.173 - 177, 2018/03
The Atomic Energy Society of Japan (AESJ) published "Guideline for Credibility Assessment of Nuclear Simulations 2015" in June, 2016 which specifies the concepts on methodology for the prediction with uncertainty quantification and the quality management based on the concept of verification and validation (V&V) of modeling and simulation. In this report, the outlines of activities in AESJ for publication of the guideline and the expectation for effective implementation of the guideline are described including that of the lectures with major respondents of the questionnaires.
Tanaka, Masaaki
Nihon Genshiryoku Gakkai Keisan Kagaku Gijutsu Bukai Nyusu Reta (Internet), (27), p.9 - 15, 2017/03
In this report, the outline of the contents in the lecture course for "Guideline for Credibility Assessment of Nuclear Simulations 2015" published in June, 2016 from the Atomic Energy Society of Japan (AESJ) and the result of the lectures held in Tokyo and Osaka are introduced with the results of the questionnaires from the audience.
Tanaka, Masaaki
no journal, ,
Guideline for Credibility Assessment of Nuclear Simulations has been established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion at the Simulation Reliability Assessment Subcommittee in the Advanced and Fundamental Systems Technical Committee (ATC), the ATC and the Standards Committee (SC). This guideline specifies the fundamental concept on the assessment of simulation credibility in the nuclear system. When the guideline is to be issued, recent status of the activities for publication of guidelines and standards related to the verification and validation inside and outside the country is introduced.
Tanaka, Masaaki
no journal, ,
In order to enhance the simulation credibility, it is necessary to establish the procedure on verification and validation including the estimation of the modeling uncertainty. Lessons learned from the Fukushima Daiichi NPP Accident have indicated that it was important to recognize the credibility of the simulation. By putting forward to standardize the procedure on verification and validation including the estimation of the modeling uncertainty, it is expected to establish the basis of the simulation technology to realize the world highest level of nuclear safety and continuous improvement. The recent activity in the Atomic Energy Society of Japan (AESJ) for the guideline establishment is introduced.
Tanaka, Masaaki
no journal, ,
Outline of the Guideline for Credibility Assessment of Nuclear Simulations which has been established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion at the Simulation Reliability Assessment Subcommittee in the Advanced and Fundamental Systems Technical Committee (ATC), the ATC and the Standards Committee (SC), is introduced and recent status of the activities for publication of guidelines and standards related to the verification and validation inside and outside the country is also introduced.
Tanaka, Masaaki
no journal, ,
A procedure called as V2UP (Verification and Validation plus Uncertainty quantification and Prediction) was made by referring to the existing guidelines on V&V and the methodologies of the safety assessment (CSAU, ISTIR, EMDAP). The V2UP consisted of five components as follows: (1) phenomena analysis with the Phenomena Identification and Ranking Table (PIRT) method, (2) implementation of the V&V, (3) design and rearrangement of experiments for the V&V, (4) uncertainty quantification in each problem and integration of uncertainties and (5) numerical prediction (estimation) for the target issue. Although the complete application of the procedure has not been performed at this moment, a flow chart of the V2UP procedure was described in this paper with recent results of the examinations.
Tanaka, Masaaki
no journal, ,
In the lecture course of "Guideline for Credibility Assessment of Nuclear Simulations: 2015", the latest situation in overseas regarding V&V activities is to be introduced during the panel discussion (Part 1).
Tanaka, Masaaki
no journal, ,
In the lecture course of "Guideline for Credibility Assessment of Nuclear Simulations: 2015", the outline of the V2UP (V&V Plus Uncertainty Quantification and Prediction) procedure for high cycle thermal fatigue in sodium-cooled fast reactor is to be introduced.
Tanaka, Masaaki
no journal, ,
In the lecture course of "Guideline for Credibility Assessment of Nuclear Simulations: 2015", the latest situation in overseas regarding V&V activities is to be introduced during the panel discussion (Part 1).
Tanaka, Masaaki
no journal, ,
In the lecture course of "Guideline for Credibility Assessment of Nuclear Simulations: 2015", the outline of the V2UP (V&V Plus Uncertainty Quantification and Prediction) procedure for high cycle thermal fatigue in sodium-cooled fast reactor is to be introduced.
Tanaka, Masaaki
no journal, ,
The Atomic Energy Society of Japan (AESJ) published "Guideline for Credibility Assessment of Nuclear Simulations 2015" in June, 2016 which specifies the concepts on methodology for the prediction with uncertainty quantification and the quality management based on the concept of verification and validation (V&V) of modeling and simulation. In this session, the outline of activities in AESJ for publication of the guideline and the expectation for effective implementation of the guideline are to be presented. And domestic and overseas activities regarding to the V&V out of the field of the nuclear energy are to be introduced.
Tanaka, Masaaki
no journal, ,
Activities of the subcommittee in Atomic Energy Society of Japan (AESJ) for the publication of "Guideline for Credibility Assessment of Nuclear Simulations 2015" are introduced and a case study of VVUQ (verification and validation plus uncertainty quantification) application to the numerical simulation of the T-junction piping system is briefly presented.
Tanaka, Masaaki
no journal, ,
In the nuclear engineering, simulations are used in radiation, thermal hydraulic, chemical reaction, and structural fields, and the integrated fields thereof, to be applied to the design, construction and operation of nuclear facilities. This document describes outline of the V&V guideline "Guideline for Credibility Assessment of Nuclear Simulations (AESJ-SC-A008: 2015)" published from AESJ. An application study of the methodologies, e.g., GCI method, area validation metrics, for verification and validation plus uncertainty quantification (VVUQ) is introduced using numerical simulation results of the fluid-structure thermal interaction analysis in a water experiment of a T-junction piping system.
Tanaka, Masaaki
no journal, ,
In the nuclear engineering, simulations are used in radiation, thermal hydraulic, chemical reaction, and structural fields, and the integrated fields thereof, to be applied to the design, construction and operation of nuclear facilities. This document describes outline of the V&V guideline "Guideline for Credibility Assessment of Nuclear Simulations (AESJ-SC-A008: 2015)" published from AESJ. An application study of the methodologies, e.g., GCI method, area validation metrics, for verification and validation plus uncertainty quantification (VVUQ) is introduced using numerical simulation results of the fluid-structure thermal interaction analysis in a water experiment of a T-junction piping system.
Tanaka, Masaaki
no journal, ,
In the nuclear engineering, simulations are used in radiation, thermal hydraulic, chemical reaction, and structural fields, and the integrated fields thereof, to be applied to the design, construction and operation of nuclear facilities. This document describes outline of the V&V guideline "Guideline for Credibility Assessment of Nuclear Simulations (AESJ-SC-A008: 2015)" published from AESJ. An application study of the methodologies, e.g., GCI method, area validation metrics, for verification and validation plus uncertainty quantification (VVUQ) is introduced using numerical simulation results of the fluid-structure thermal interaction analysis in a water experiment of a T-junction piping system.
