Proposal of benchmark problem of thermal striping phenomena in planar triple parallel jets tests for fundamental code validation in sodium-cooled fast reactor development

Kobayashi, Jun; Tanaka, Masaaki; Ohno, Shuji; Ohshima, Hiroyuki; Kamide, Hideki

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.6664 - 6677, 2015/08

Numerical simulation is recognized an essential tool for the physical phenomena analysis and plant design study of a sodium-cooled fast reactor (SFR). In order to enhance credibility of the numerical results in the activities for plant design by using numerical simulations, it is recognized that verification and validation (V&V) process is very important. In this study, experiments for planar triple parallel jets mixing phenomena conducted in JAEA were proposed as benchmark problems for the code validation in the area of thermal striping study in the SFR development.

Proposal and analysis of the benchmark problem suite for reactor physics study of LWR next generation fuels

Research Committee on Reactor Physics

JAERI-Research 2001-046, 326 Pages, 2001/10

JAERI-Research-2001-046.pdf:14.45MB

The Working Party on Reactor Physics for LWR Next Generation Fuels in the Research Committee on Reactor Physics, which is organized by the Japan Atomic Energy Research Institute, has recently proposed a series of benchmark problems to investigate the calculation accuracy of the nuclear characteristics of LWR next generation fuels. The next generation fuels mean the ones aiming for further extended burnup such as 70GWd/t over the current design. The resultant specifications of the benchmark problem therefore neglect some of the current limitations such as 5wt%235U to achieve the above-mentioned target. The Working Party proposed six benchmark problems, which consist of pin-cell, PWR assembly and BWR assembly geometries loaded with uranium and MOX fuels, respectively. The present report describes the detailed specifications of the benchmark problems. The results of preliminary analyses performed by the eleven member organizations and their comparisons are also presented.

Analytical evaluation on loss of off-site electric power simulation of the High Temperature Engineering Test Reactor

Takeda, Takeshi; Nakagawa, Shigeaki; Tachibana, Yukio; Takada, Eiji*; Kunitomi, Kazuhiko

JAERI-Research 2000-016, p.80 - 0, 2000/03

JAERI-Research-2000-016.pdf:2.72MB

no abstracts in English

Benchmark calculation of subchannel analysis codes

JAERI-Data/Code 96-004, 109 Pages, 1996/02

JAERI-Data-Code-96-004.pdf:2.3MB

no abstracts in English

Benchmark problems for intermediate and high energy accelerator shielding

; Sakamoto, Yukio; Tanaka, Shunichi; ; Fukahori, Tokio; ; Sasamoto, Nobuo; Tanaka, Susumu; Nakamura, Takashi*; Shin, Kazuo*; et al.

JAERI-Data/Code 94-012, 90 Pages, 1994/09

JAERI-Data-Code-94-012.pdf:2.26MB

no abstracts in English

Solutions to NEANSC benchmark problems on Power Distribution within Assemblies(PDWA) using the SRAC and GMVP

Kugo, Teruhiko; Nakagawa, Masayuki;

JAERI-M 92-117, 70 Pages, 1992/08

JAERI-M-92-117.pdf:1.39MB

no abstracts in English

EISPACK-J: Subprogram Package for Solving Eigenvalue Problems; Development and Benchmark Test of SSL, No.8

;

JAERI-M 8253, 133 Pages, 1979/05

JAERI-M-8253.pdf:4.0MB

no abstracts in English

Benchmark tests of radiation transport computer codes for reactor core and shield calculations

; ; ; ; ; ; ; ; ; ; et al.

Journal of Nuclear Science and Technology, 15(1), p.56 - 71, 1978/01

https://doi.org/10.3327/jnst.15.56

no abstracts in English