Refine your search:     
Report No.
 - 
Search Results: Records 1-6 displayed on this page of 6
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Validation of the TAC-NC code through the experimental results of safety demonstration test using the HTTR

Takamatsu, Kuniyoshi; Nakagawa, Shigeaki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.369 - 380, 2004/12

This paper describes the validation of the TAC-NC code using the measured value of the test by tripping of one and two out of three gas circulators at 30% (9MW). By upgrading the code, the analytical result can evaluate accurately the measured value of the transient temperature distribution within 20$$^{circ}$$C. Also, the improved code can analyze the maximum fuel temperature and temperature distributions of the test by tripping all the three gas circulators. The result of this study can be applied to development for not only the commercial HTGRs but also the Very High Temperature Reactor (VHTR) such as one of the Generation IV reactors.

JAEA Reports

Natural convection tests with the in-core structure test section (T$$_{2}$$) of the helium engineering demonstration loop (HENDEL)

Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Ioka, Ikuo; Sudo, Yukio

JAERI-Research 95-048, 41 Pages, 1995/07

JAERI-Research-95-048.pdf:1.22MB

no abstracts in English

JAEA Reports

Design of fusion safety data base

Aoki, Isao; Seki, Yasushi

JAERI-M 94-044, 63 Pages, 1994/03

JAERI-M-94-044.pdf:1.27MB

no abstracts in English

JAEA Reports

Safety demonstration test plan in the High Temperature Engineering Test Reactor(HTTR) and their safety evaluation

Kunitomi, Kazuhiko; Maruyama, So; Shindo, Masami; Sudo, Yukio

JAERI-M 90-070, 46 Pages, 1990/04

JAERI-M-90-070.pdf:1.29MB

no abstracts in English

Journal Articles

Principles of PIUS: Some safety-related characteristics

Asahi, Yoshiro; *

Transactions of the American Nuclear Society, 47, p.297 - 298, 1984/00

no abstracts in English

Oral presentation

The International PRIME partnership; An Opportunity to help ensure successful near-term deployments of modern HTGRs

Haynes, M.*; Wrochna, G.*; Kunitomi, Kazuhiko

no journal, , 

The Prismatic Block HTGR is a mature, intrinsically safe, and extremely versatile energy technology that can proceed to full development and licensing almost immediately resulting in a completed FOAK demonstration within 15 years. A high level of interest in this technology exists in Poland, the U.S., Japan, Korea and other countries. The proposed international PRIME partnership centers on two concepts: (1) Parallel deployments of very similar, but market-appropriate sized prismatic block HTGRs (7500$$^{circ}$$C outlet temperature) for industrial process heat in both the U.S. and Poland; and (2) A longer-term development program to increase reactor outlet temperatures for hydrogen production, etc. We believe that the PRIME partnership can reduce development and licensing costs for each of our countries, expand international markets, and help attract and sustain the funding and political support necessary to ensure successful FOAK deployments. This paper will describe in more detail the PRIME Partnership and its justifications.

6 (Records 1-6 displayed on this page)
  • 1