Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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.

4 (Records 1-4 displayed on this page)
  • 1