Benchmark simulation code for the thermal-hydraulics design tool of the accelerator-driven system; Validation and benchmark simulation of flow behavior around the beam window

Yamashita, Susumu; Kondo, Nao; Sugawara, Takanori; Monji, Hideaki*; Yoshida, Hiroyuki

Journal of Nuclear Science and Technology, 22 Pages, 2023/00

https://doi.org/10.1080/00223131.2023.2268676

To confirm the validity of the thermal-hydraulics design tool based on the Ansys Fluent, we used a detailed computational fluid dynamics code named JAEA Utility Program for Interdisciplinary Thermal-hydraulics Engineering and Research (JUPITER) for the thermal-hydraulics around the beam window (BW) of the Accelerator-Driven System (ADS). The Fluent uses the Reynolds-Averaged Navier-Stokes (RANS) model and can quickly calculate the turbulent flow around the BW as a BW design tool. At first, we compared the results of JUPITER with the experimental results using a mock-up BW system in water to confirm the validity of JUPITER. As a result, we confirmed that numerical results are in good agreement with the experimental results. Thus, we showed that JUPITER could be used as a benchmark code. We also performed a benchmark simulation for the Fluent calculation using validated JUPITER to show the applicability of JUPITER as an alternative of experiments. As a result, the mean values around the BW agreed with each other, e.g., the mean velocity profile for stream and horizontal directions. Therefore, we confirmed that JUPITER showed a good performance in validating the thermal-hydraulics design tool as a fluid dynamics solver. Moreover, Fluent has enough accuracy as a thermal-hydraulics design tool for the ADS.

Present status and future perspective of R&D for 3D-ADRES (3-Dimensional Air Dose Rate Evaluation System); Evaluation scheme for air dose rate distributions in city and forest areas towards Fukushima's revitalization

Kim, M.; Malins, A.; Machida, Masahiko; Yoshimura, Kazuya; Saito, Kimiaki; Yoshida, Hiroko*; Yanagi, Hideaki*; Yoshida, Toru*; Hasegawa, Yukihiro*

RIST News, (67), p.3 - 15, 2021/09

https://www.rist.or.jp/rnews/67/ristnews_67.html

no abstracts in English

Towards optimizing the performance of self-regenerating Pt-based perovskite catalysts

Jarrige, I.*; Ishii, Kenji; Matsumura, Daiju; Nishihata, Yasuo; Yoshida, Masahiro*; Kishi, Hirofumi*; Taniguchi, Masashi*; Uenishi, Mari*; Tanaka, Hirohisa*; Kasai, Hideaki*; et al.

ACS Catalysis, 5(2), p.1112 - 1118, 2015/02

https://doi.org/10.1021/cs501608k

Development of prediction technology of two-phase flow dynamics under earthquake acceleration, 14; Numerical simulation of two-phase flow in subchannels under accelerating condition

Yoshida, Hiroyuki; Nagatake, Taku; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*

Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 10 Pages, 2014/07

https://doi.org/10.1115/ICONE22-30153

Numerical simulation of rising bubble behavior under accelerating conditions

Yoshida, Hiroyuki; Nagatake, Taku; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*

Dai-62-Kai Riron Oyo Rikigaku Koenkai Koen Rombunshu (USB Flash Drive), 2 Pages, 2013/03

https://www.jstage.jst.go.jp/article/japannctam/62/0/62_54/_article/-char/ja/

no abstracts in English

Numerical prediction of two-phase flow behavior under seismic condition by use of interface tracking method

Yoshida, Hiroyuki; Nagatake, Taku; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*

Nihon Kikai Gakkai Dai-25-Kai Keisan Rikigaku Koenkai Rombunshu (CD-ROM), p.693 - 695, 2012/10

no abstracts in English

Numerical simulation of two-phase flow behavior under earthquake acceleration

Yoshida, Hiroyuki; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*

Proceedings of IEEE PES Asia-Pacific Power and Energy Engineering Conference 2012 (APPEEC 2012) (CD-ROM), 4 Pages, 2012/03

https://doi.org/10.1109/APPEEC.2012.6307082

The second maintenance report at plutonium conversion development facility

; ; *; *; *; *; *

JNC TN8440 2000-013, 179 Pages, 2000/04

JNC-TN8440-2000-013.pdf:10.31MB

The plutonium conversion development facility (PCDF) has been operated for 17 years and about 12 tons plutonium-uranium mixed oxide (MOX) powder has been converted since operation started in 1983. The first maintenance program for aging of apparatus was carried out from 1993 to 1994. The calcination-reduction fumace, liquid waste evaporator had been dismantled and renewed. The second maintenance program was carried out form 1998 to 1999. The microwave ovens, powder blender, ventilation control panel and so on were dismantled and renewed. Large volume radioactive wastes were generated during this maintenance such as the furnace, the filter casings and glove boxes. These wastes were too large to be packed into the waste container and these wastes were polluted by MOX powder unfixed on these surface. SO cutting and packing operation for these wastes and recovery of MOX powder from them were carried out. In this report, the method of this cutting and packing operation, the radioactive exposure to the operators in this operation, the estimation of nuclear material quantity migrated to filters, the evaluation of re-floating factor of radioactive material, etc. were discussed.

Origin identification of building stone using prompt -ray analysis

Matsue, Hideaki; Ojima, Hitoshi*; Yoshida, Hirokazu*; Asano, Nobuko*; Hasegawa, Shoichi*; Cho, Akio*; Hatsukawa, Yuichi; Segawa, Mariko; Osawa, Takahito; Numao, Tatsuya*; et al.

no journal, , 

no abstracts in English

Development of prediction technology of two-phase flow dynamics under earthquake acceleration, 1; Numerical simulation of two-phase flow behavior under earthquake acceleration

Yoshida, Hiroyuki; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*

no journal, ,