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Journal Articles

Development of an RPV cooling system for HTGRs

Takamatsu, Kuniyoshi

Kakushinteki Reikyaku Gijutsu; Mekanizumu Kara Soshi, Shisutemu Kaihatsu Made, p.179 - 183, 2024/01

The HTGR has excellent safety, and even in the event of an accident where the reactor coolant is lost, the decay heat and residual heat in the core can be dissipated from the outer surface of the RPV, so the fuel temperature never exceeds the limit value, and the core stabilizes. On the other hand, regarding the cooling system that transports the heat emitted from the RPV to the final heat sink, an active cooling system using forced circulation of water by a pump, etc., and a passive cooling system using natural circulation of the atmosphere have been proposed. However, there is a problem that the cooling performance is affected by the operation of dynamic equipment and weather conditions. This paper presents an overview of a new cooling system concept using radiative cooling, which has been proposed to solve the above problem, and introduces the results of analysis and experiments aimed at confirming the feasibility of this concept.

Journal Articles

Improvement of cooling performance of reactor pressure vessel using passive cooling

Banno, Masaki*; Funatani, Shumpei*; Takamatsu, Kuniyoshi

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 7 Pages, 2023/05

A fundamental study on the safety of a passive cooling system for the RPV with radiative cooling is conducted. The object of this study is to demonstrate that passive RPV cooling system with radiative cooling is extremely safe and reliable even in the event of natural disasters. Therefore, an experimental apparatus, which is about 1/20 scale of the actual cooling system, was fabricated with several stainless steel containers. The surface of the heating element in the experimental apparatus simulates the surface of the RPV, and the heating element generates natural convection and radiation. A comparison of the Grashof number between the actual cooling system and the experimental apparatus confirmed that both were turbulent, and the experimental results as a scale model are valuable. Moreover, the experimental results confirmed that the heat generated from the surface of the RPV during the rated operation can be removed.

Journal Articles

Study on heat transfer characteristics of reactor cavity cooling system using radiation

Banno, Masaki*; Funatani, Shumpei*; Takamatsu, Kuniyoshi

Yamanashi Koenkai 2022 Koen Rombunshu (CD-ROM), 6 Pages, 2022/10

A fundamental study on the safety of a passive cooling system for the reactor pressure vessel (RPV) with radiative cooling is conducted. The object of this study is to demonstrate that passive RPV cooling system with radiative cooling is extremely safe and reliable even in the event of natural disasters. Therefore, an experimental apparatus, which is about 1/20 scale of the actual cooling system, was fabricated with several stainless steel containers. The surface of the heating element in the experimental apparatus simulates the surface of the RPV, and the heating element generates natural convection and radiation. As a result of the experiments, we succeeded in visualizing the natural convection in the experimental apparatus in detail.

JAEA Reports

Report of the review committee on evaluation of the R&D subjects in the field of nuclear safety research

Research Evaluation Committee

JAERI-Review 2000-021, 36 Pages, 2000/09

JAERI-Review-2000-021.pdf:3.01MB

no abstracts in English

JAEA Reports

None

JNC TN1400 99-017, 439 Pages, 1999/08

JNC-TN1400-99-017.pdf:14.06MB

no abstracts in English

JAEA Reports

None

Miyo, Hiroaki; ; Kudo, Kenji; Sukegawa, Yasuhiro*

JNC TN8440 99-005, 864 Pages, 1999/03

JNC-TN8440-99-005.pdf:40.45MB

None

JAEA Reports

None

PNC TJ1612 98-001, 77 Pages, 1998/03

PNC-TJ1612-98-001.pdf:2.42MB

no abstracts in English

JAEA Reports

None

PNC TN1410 97-045, 24 Pages, 1997/12

PNC-TN1410-97-045.pdf:8.07MB

no abstracts in English

Journal Articles

Tritium technology research and development at the tritium process laboratory of JAERI

Okuno, Kenji; Konishi, Satoshi; Yamanishi, Toshihiko; Ohira, Shigeru; Enoeda, Mikio; Nakamura, Hirofumi; Iwai, Yasunori; Hayashi, Takumi; Kawamura, Yoshinori; Kobayashi, Kazuhiro

Fusion Technology 1996, p.1277 - 1280, 1997/00

no abstracts in English

JAEA Reports

None

PNC TN8440 95-042, 113 Pages, 1995/09

PNC-TN8440-95-042.pdf:2.98MB

None

JAEA Reports

None

PNC TN8440 93-045, 104 Pages, 1993/09

PNC-TN8440-93-045.pdf:2.68MB

None

JAEA Reports

None

Matsumoto, Shiro*

PNC TJ1533 93-001, 339 Pages, 1993/03

PNC-TJ1533-93-001.pdf:10.31MB

no abstracts in English

JAEA Reports

None

; Kajiyama, Tadashi; ; Nakashima, Yuji; ; ;

PNC TN9520 92-001, 17 Pages, 1991/10

PNC-TN9520-92-001.pdf:0.53MB

None

JAEA Reports

Survey of Researches on LWR Containment Spray Effectiveness

JAERI-M 7481, 151 Pages, 1978/01

JAERI-M-7481.pdf:4.21MB

no abstracts in English

Journal Articles

On the safety and failsafe for reactor control

;

Shisutemu To Seigyo, 18(7), p.396 - 402, 1974/07

no abstracts in English

Oral presentation

Research on Reactor Cavity Cooling System (RCCS) with passive safety features

Takamatsu, Kuniyoshi; Funatani, Shumpei*; Banno, Masaki*

no journal, , 

After Fukushima Daiichi nuclear disaster, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. Specifically, the decay heat can be passively removed for a long time, even forever if the heat removal capacity of the RCCS is sufficient.

18 (Records 1-18 displayed on this page)
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