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Journal Articles

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger, 2; Study of sodium-molten salt heat exchanger heat transfer performance

Hayashi, Masaaki*; Nakahara, Hirotaka*; Shirakura, Shota*; Yamano, Hidemasa

Proceedings of International Conference on Nuclear Fuel Cycle (GLOBAL2024) (Internet), 4 Pages, 2024/10

As part of the development of risk assessment technologies for sodium-cooled fast reactor coupled to thermal energy storage (TES) system with sodium-molten salt heat exchanger (HX), simple evaluation of heat transfer performance using heat transfer coefficient formula is performed. And Computational Fluid Dynamics (CFD) thermal analyses by STAR-CCM+ with partial HX model are performed to develop evaluation technology. The performance evaluation technology of a HX between sodium and molten salt and the confirmation of heat transfer improvement measures effects is developed.

Journal Articles

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger, 1; Overview and Consideration on tube failure

Yamano, Hidemasa; Takano, Kazuya; Kurisaka, Kenichi; Kikuchi, Shin; Kondo, Toshiki; Umeda, Ryota; Sato, Rika; Shirakura, Shota*

Dai-28-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2024/06

This project studies investigation on safety design guideline and risk assessment technology for sodium-cooled fast reactor with the molten-salt heat storage system, development of evaluation method for heat transferring performance between sodium and molten-salt and improvement of the performance, and evaluation of chemical reaction characteristic between sodium and molten-salt and improvement of its safety. This paper describes the effect of sodium-molten salt heat transfer tube failure in addition to the project overview and progress.

Journal Articles

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger, 2; Study on heat exchanger performance

Hayashi, Masaaki*; Nakahara, Hirotaka*; Abe, Takashi*; Matsunaga, Suhei*; Miyata, Hajime*; Shirakura, Shota*; Yamano, Hidemasa

Dai-28-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2024/06

This paper describes the study of the performance evaluation technology of a heat exchanger between sodium and molten salt and the confirmation of heat transfer improvement measures effects up to FY2023.

Journal Articles

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger; Project overview

Yamano, Hidemasa; Kurisaka, Kenichi; Takano, Kazuya; Kikuchi, Shin; Kondo, Toshiki; Umeda, Ryota; Shirakura, Shota*

Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2023/09

This project studies investigation on safety design guideline and risk assessment technology for sodium-cooled fast reactor with the molten-salt heat storage system, development of evaluation method for heat transferring performance between sodium and molten-salt and improvement of the performance, and evaluation of chemical reaction characteristic between sodium and molten-salt and improvement of its safety. The project overview is presented in this report.

JAEA Reports

Overhaul of the Primary cooling system heat exchanger in JRR-3

Uno, Yuki; Ouchi, Yasuhiro; Ouchi, Satoshi; Baba, Ryota; Kikuchi, Masanobu; Kawamata, Satoshi

JAEA-Technology 2021-046, 39 Pages, 2023/02

JAEA-Technology-2021-046.pdf:3.76MB

JRR-3 (Japan Research Reactor No.3) is a light water research reactor cooling pool type light water deceleration of low-enriched uranium up to 20MW thermal power. November 1990, begin to operation in modified that we are provided to users as a high neutron flux form reactor facility in various types of irradiation facilities and neutron beam experiment equipment. Currently, JRR-3 has completed the period of facility inspections, which had been extended due to the effects of the Great East Japan Earthquake of March 11, 2011, and has been able to conformity to the New Regulatory Requirements. It has also resumed operation for the first time in about 10 years. FY 2017, overhauled the primary cooling heat exchanger No.1 and No.2 based on a maintenance plan. This is report for take advantage what inspection and maintenance of future about overhaul of the primary cooling system heat exchanger for collect of inspection records and performance.

Journal Articles

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger

Yamano, Hidemasa; Kurisaka, Kenichi; Takano, Kazuya; Kikuchi, Shin; Kondo, Toshiki; Umeda, Ryota; Shirakura, Shota*; Hayashi, Masaaki*

Proceedings of 8th International Conference on New Energy and Future Energy Systems (NEFES 2023) (Internet), p.27 - 34, 2023/00

 Times Cited Count:0 Percentile:0.00(Green & Sustainable Science & Technology)

This project studies investigation on safety design guideline and risk assessment technology for sodium-cooled fast reactor with the molten-salt heat storage system, development of evaluation method for heat transferring performance between sodium and molten-salt and improvement of the performance, and evaluation of chemical reaction characteristic between sodium and molten-salt and improvement of its safety. The project overview is presented in this report.

Journal Articles

Seismic capacity evaluation of a group of vertical U-tube heat exchanger with support frames for seismic PSA

Watanabe, Yuichi*; Muramatsu, Ken; Oikawa, Tetsukuni

Nuclear Engineering and Design, 235(23), p.2495 - 2512, 2005/12

 Times Cited Count:2 Percentile:17.10(Nuclear Science & Technology)

This paper presents an evaluation of seismic capacity of a group of vertical U-tube type heat exchangers(HXs) with support frames for residual heat removal systems of BWRs for seismic Probabilistic Safety Assessment in Japan. The median capacity was evaluated by a time history response analysis with a detailed model for a representative HX selected from four HXs. The logarithmic standard deviation(LSD) for uncertainty due to lack of knowledge was evaluated with consideration of the variabilities in three influential parameters, i.e., diameter of anchor bolt, weight of HX and position of center of gravity of HX. The dominant failure mode of HXs was the failure of anchor bolts of lugs mainly due to shearing stress. The capacity expressed in terms of zero period acceleration on the foundation of HX was evaluated to be 4,180 Gal(4.3 g) for median, LSD for uncertainty due to randomness was 0.11 from the variability in material property and LSD due to lack of knowledge was 0.21 to 0.53 depending on combination of the variability in design parameters to be considered.

JAEA Reports

Management techniques of the JRR-4 heat exchanger

Horiguchi, Hironori; Oyama, Koji; Ishikuro, Yasuhiro; Hirane, Nobuhiko; Ito, Kazuhiro; Kameyama, Iwao

JAERI-Tech 2005-001, 38 Pages, 2005/02

JAERI-Tech-2005-001.pdf:2.79MB

After JRR-4 heat exchanger was renewed in made of stainless steel from carbon steel, it was examined how to manage the heat exchanger. The main subject is the cleaning technology of the heat exchanger. The recovery of old heat exchanger cooling performance has been by only chemical cleaning. Now we use chemical and dry cleaning as a new technique. It helps prevent of corrosions of secondary pipes and reduce of management costs. This report describes the performance management and cleaning technology of the JRR-4 heat exchanger and the management of the JRR-4 coolant.

Journal Articles

Mechanical properties on multi stage blazed fin body with ultra fine off-set fin for compact heat exchager at Elevated Temperature

Ishiyama, Shintaro

Nihon Kinzoku Gakkai-Shi, 68(7), p.490 - 497, 2004/07

 Times Cited Count:0 Percentile:0.00(Metallurgy & Metallurgical Engineering)

SUS304 multi stage blazed fin core body for GTHTR300 was tested its high temperature strength, fatigue and creep and it was found that the body behaves as same strength of SUS304 material.

Journal Articles

Study of power conversion unit design of Gas Turbine High Temperature Reactor (GTHTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Minatsuki, Isao*

Dai-31-Kai Gasu Tabin Teiki Koenkai Rombunshu, p.55 - 60, 2003/06

no abstracts in English

Journal Articles

Stress analysis of plate-fin type heat exchanger

Matsui, Shingo*; Muto, Yasushi*; Shiina, Yasuaki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.175 - 186, 2003/06

no abstracts in English

Journal Articles

High temperature mechanical properties on multi stage blazed fin body with ultra fine off-set fin for compact heat exchanger

Ishiyama, Shintaro; Muto, Yasushi

Nihon Kikai Gakkai Rombunshu, A, 69(679), p.682 - 688, 2003/03

no abstracts in English

Journal Articles

Design study of power conversion system for the Gas Turbine High Temperature Reactor (GTHTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Kosugiyama, Shinichi; Minatsuki, Isao*; Miyoshi, Yasuyuki*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.341 - 351, 2002/12

no abstracts in English

Journal Articles

Heat transfer characteristics of a steam reformer inserted metallic wire

Takeda, Tetsuaki

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.199 - 202, 2002/00

There are several methods for enhancement of heat transfer such as attaching various type fins on a channel surface of a heat exchanger tube and a steam reforming tube. The objective of this study is to clarify characteristics of heat transfer and pressure drop in the channel inserted metallic wire with high porosity. A heat transfer experiment was performed using a horizontal circular tube to obtain the heat transfer characteristics of the channel inserted copper wire. From the results obtained in this experiment, it seems to be probable that an enhancement of heat transfer method using metallic wire inserts is further improved under the high temperature conditions in efficiency as compared with the other methods.

Journal Articles

Design of power conversion system of Gas Turbine High Temperature Reactor (GTGTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Kosugiyama, Shinichi; Shiozawa, Shusaku

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.189 - 192, 2002/00

no abstracts in English

Journal Articles

The Effect of unbalance flow on the performance of compact heat exchanger for HTGR-GT system

Ishiyama, Shintaro; Muto, Yasushi; Ogata, Hiroshi*; Yamada, Seiya*

Nihon Genshiryoku Gakkai-Shi, 43(11), p.1136 - 1148, 2001/11

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of the compact heat exchanger for HTGR, 1; Fabrication of the ultra fine off-set fin

Ishiyama, Shintaro; Muto, Yasushi; Tanihira, Masanori*; Ogata, Kan*; Kamito, Yoshimi*; Igari, Toshihide*

Nihon Genshiryoku Gakkai-Shi, 43(6), p.603 - 611, 2001/06

 Times Cited Count:4 Percentile:32.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Computer simulation analysis on the machinability of alumina dispersion enforced copper alloy for high performance compact heat exchanger

Ishiyama, Shintaro; Muto, Yasushi; Nishii, Takashi*; Kasaba, Michihiro*

Nihon Kinzoku Gakkai-Shi, 65(6), p.524 - 533, 2001/06

no abstracts in English

JAEA Reports

Stress analysis of plate-fin structures in recuperator

Matsui, Shingo*; Muto, Yasushi; Shiina, Yasuaki

JAERI-Tech 2000-083, 107 Pages, 2001/01

JAERI-Tech-2000-083.pdf:3.46MB

no abstracts in English

Journal Articles

Technical issues and their solutions in HTGR gas turbine system

Muto, Yasushi; Ishiyama, Shintaro

Nihon Genshiryoku Gakkai-Shi, 42(10), p.1020 - 1027, 2000/10

 Times Cited Count:1 Percentile:11.79(Nuclear Science & Technology)

no abstracts in English

82 (Records 1-20 displayed on this page)