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Journal Articles

Numerical simulation of thermal striping phenomena for fundamental validation and uncertainty quantification; Application of least square version GCI and area validation method to impinging jet in a T-Junction piping system

Tanaka, Masaaki

Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) (USB Flash Drive), 14 Pages, 2018/10

A numerical simulation code MUGTHES has been developed to estimate high cycle thermal fatigue in SFRs. In development of numerical simulation code, verification, validation, and uncertainty quantification (VVUQ) are indispensable. In this study, numerical simulation at impinging jet condition in the WATLON experiment which was the water experiment of a T-junction piping system was performed for the fundamental validation. Based on the previous studies, the simplified least square version GCI method and the area validation metrics were employed as reference methods to quantify uncertainty and to measure the degree of difference between the numerical and the experimental results, respectively. Through the examinations, the potential applicability of the MUGTHES to the thermal striping phenomena was indicated and requirements of modification in the simulation was suggested in accordance with the uncertainty values.

Journal Articles

Development of V2UP (Verification & Validation plus Uncertainty quantification and Prediction) procedure for high cycle thermal fatigue in fast reactor; A Challenge to implementation of quality management

Tanaka, Masaaki

Keisan Kogaku Koenkai Rombunshu (CD-ROM), 22, 4 Pages, 2017/05

In the development of the simulation code and the numerical estimation for high cycle thermal fatigue on a structure caused by thermal striping phenomena in sodium cooled fast reactors, implementation of verification and validation (V&V) process is indispensable. A procedure named V2UP (Verification and Validation plus Uncertainty quantification and Prediction) has been made by referring to the existing guidelines regarding the V&V and the methodologies of the safety assessment. In this paper, a challenging installation of quality management procedures into the V2UP procedure is attempted based on the JSCES Standard for "A Model Procedure for Engineering Simulation".

Oral presentation

Current status and future perspective of the Verification and Validation (V&V) of JENDL and neutronics calculation codes by use of the benchmark problems and integral experiments, 1; International benchmarks of OECD/NEA in the field of the neutronics calculation

Suyama, Kenya

no journal, , 

We, researchers of Japan, have been participating in numerous international neutronics computer code benchmarks organized by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA) for many years. This presentation shows examples of the international computer code benchmarks which the speaker has been involved and the role of the benchmarks for the verification and validation of computer codes in future would be discussed.

Oral presentation

Verification & validation for quantity evaluation code

Nishihara, Kenji; Takeshita, Kenji*; Shimada, Takashi*; Nakase, Masahiko*

no journal, , 

Many codes have been developed in the world to quantify future nuclear scenarios for the purpose of developing nuclear energy utilization strategies and R&D goals. However, quality assurance and verification of the accuracy of the codes are not yet fully implemented, with only simple benchmark intercomparisons by the OECD/NEA. In the various evaluation codes, many models are used for each process of the nuclear fuel cycle and nuclear reactors, and there are differences in the definitions of inputs and outputs and databases, so a general verification method has not been established. Therefore, we developed a verification and validation (V&V) method for quantity evaluation codes to contribute to quality assurance and accuracy verification in the future.

Oral presentation

Discussion towards formulating V&V guidelines regarding radiation shielding analysis, 1; System of verification and validation for dissemination and maintenance of national codes and data

Suyama, Kenya

no journal, , 

The importance of verification and validation (V&V) of computational codes and databases is well recognized in Japan. Whenever R&D projects centering on computer simulations in other countries come into the limelight, the need to establish such a V&V system in Japan has been pointed out. It has been pointed out in Japan that it is necessary to establish a system for V&V of computer simulation projects in Japan as well. In the case of codes developed in industry, code development is managed according to the quality assurance process customers require. A V&V system should have been established in each organization, even if there are differences in the level of V&V. However, the V&V system for so-called "publicly available codes" has not been established in Japan. However, the V&V of so-called publicly available code depends on the individual efforts of code developers and some users, and there is no system in Japan to implement it officially as an organization. In this presentation, I would like to discuss the reasons for this and what should be done to change the current situation.

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