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Journal Articles

Feasibility Studies on Pu and MA Burning in Fast Reactor

; Takahashi, Katsuro; Yanagisawa, Tsutomu

Nuclear Technology, 118, p.14 - 25, 1998/00

 Times Cited Count:21 Percentile:82.17(Nuclear Science & Technology)

None

Journal Articles

Design Study of the Advanced Recycle System using Molten Salt

Kakehi, Isao; ; ; ; Yonezawa, Shigeaki; Takahashi, Katsuro

Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/10

None

Journal Articles

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; Takahashi, Katsuro; ; ; Nagai, Shuichiro;

Donen Giho, (100), p.69 - 85, 1996/12

None

JAEA Reports

None

*; *; *; *; *; *

PNC TN1410 93-053, 271 Pages, 1993/11

PNC-TN1410-93-053.pdf:12.81MB

no abstracts in English

Journal Articles

None

Takahashi, Katsuro

最新核エネルギー論; 最新科学論シリーズ9, 0 Pages, 1990/00

None

JAEA Reports

Long-term R&D plan on LMFBR safety research; Reactor safety R&D plan

*; *; *

PNC TN908 84-02, 367 Pages, 1984/03

PNC-TN908-84-02.pdf:11.94MB

A long-term program plan was explored by the members of Reactor Safety Section(RSS), O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation(PNC) for the future research and development(R&D) on the safety of liquid-metal fast breeder reactors(LMFBRs). The main objeetives of this program plan are to fulfill the requirements raised during the licensing of Monju, and to support the conceptual design and licensing of a future demonstration plant. The current program plan is restricted to R&D areas on the assessmpnt of reliability or integrity of the reactor primary system, which is the ultimate goal of PNC/RSS. Key issues are extracted based on the detailed review of the current status and understanding of the individual R&D areas. They are discussed in this report with emphasizing their needs and priorities. In summary, the future R&D in PNC/RSS should be directed toward: (1)Continuation of the developlment, improvement and verification of the large safety analysis codes such as SAS and SIMMER; (2)Continuation and initiation of out-of-pile and in-pile experimental studies to verify the above computer codes; (3)Continuation of international participation in the large code developments and in-pile experiments; (4)Initiation of an experimental study on the behavior of the molten core materials which is important in assessing the thermal consequences of an accident; (5)Method development for a mechanistic post-accident heat removal analysis; and (6)Scenario development on local-fault sequences to achieve the early detection and termination of the accidents.

JAEA Reports

None

Miyazaki, Keiji*; *

PNC TN951 80-02, 69 Pages, 1980/02

PNC-TN951-80-02.pdf:2.44MB

no abstracts in English

Journal Articles

None

Nakajima, Ichiro; Sasao, Nobuyuki; Kaneko, Hiromitsu; Takahashi, Katsuro

Bunri, Sakugen Joho Kokan Kaigi, , 

None

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