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Journal Articles

Study of stellar reactions in explosive hydrogen burning with CRIB

Kubono, Shigeru*; Teranishi, Takashi*; Notani, Masahiro*; Yamaguchi, Hidetoshi*; Saito, Akito*; He, J. J.*; Wakabayashi, Yasuo*; Fujikawa, Hisashi*; Amadio, G.*; Baba, Hidetada*; et al.

Nuclear Physics A, 758, p.733 - 736, 2005/07

 Times Cited Count:1 Percentile:14.45(Physics, Nuclear)

With using $$^{17}F$$ RNB from CRIB, proton inelastic scattering was observed. From this experiment, some resonance parameters have been deduced for the key reaction, $$^{14}O(alpha,p)^{17}F$$ at the explosive hydrogen burning stage in stars. Proton inelastic scattering of $$^{23}Mg$$ are also reported.

Journal Articles

Achievement of reactor-outlet coolant temperature of 950$$^{circ}$$C in HTTR

Fujikawa, Seigo; Hayashi, Hideyuki; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo; Nakagawa, Shigeaki; Sakaba, Nariaki

Journal of Nuclear Science and Technology, 41(12), p.1245 - 1254, 2004/12

 Times Cited Count:89 Percentile:97.75(Nuclear Science & Technology)

A High Temperature Gas-cooled Reactor (HTGR) is particularly attractive due to its capability of producing high-temperature helium gas and to its inherent safety characteristics. The High Temperature Engineering Test Reactor (HTTR), which is the first HTGR in Japan, achieved its rated thermal power of 30MW and reactor-outlet coolant temperature of 950$$^{circ}$$C on 19 April 2004. During the high-temperature test operation which is the final phase of the rise-to-power tests, reactor characteristics and reactor performance were confirmed, and reactor operations were monitored to demonstrate the safety and stability of operation. The reactor-outlet coolant temperature of 950$$^{circ}$$C makes it possible to extend high-temperature gas-cooled reactor use beyond the field of electric power. Also, highly effective power generation with a high-temperature gas turbine becomes possible, as does hydrogen production from water. The achievement of 950$$^{circ}$$C will be a major contribution to the actualization of producing hydrogen from water using the high-temperature gas-cooled reactors. This report describes the results of the high-temperature test operation of the HTTR.

Journal Articles

JAERI completed performance tests of the High Temperature Engineering Test Reactor (HTTR) at 950$$^{circ}$$C

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo

Nihon Genshiryoku Gakkai-Shi, 46(8), P. 510, 2004/08

no abstracts in English

Journal Articles

High Temperature Engineering Test Reactor (HTTR) of JAERI achieved the reactor outlet helium gas temperature of 950$$^{circ}$$C for the first time in the world

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo

Nihon Genshiryoku Gakkai-Shi, 46(5), P. 301, 2004/05

no abstracts in English

Journal Articles

Rise-to-power test of the HTTR (High Temperature Engineering Test Reactor)

Fujikawa, Seigo; Okubo, Minoru; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.361 - 372, 2002/12

no abstracts in English

JAEA Reports

Study on storage and reprocessing concept of the High Temperature Engineering Test Reactor (HTTR) fuel

Sawa, Kazuhiro; Fujikawa, Seigo; Yoshimuta, Shigeharu*; Kato, Shigeru*

JAERI-Research 2001-034, 20 Pages, 2001/05

JAERI-Research-2001-034.pdf:1.68MB

no abstracts in English

Journal Articles

High temperature gas-cooled reactor

Fujikawa, Seigo

Genshiryoku Nenkan 2000/2001-Nen Ban, p.209 - 214, 2000/10

no abstracts in English

Journal Articles

High temperature gas-cooled reactor

Fujikawa, Seigo; Hagiwara, Masaki

Genshiryoku Nenkan 1999/2000-Nen Ban, p.173 - 177, 1999/00

no abstracts in English

Journal Articles

Study on storage and reprocessing concept of the High Temperature engineering Test Reactor (HTTR) fuel

Sawa, Kazuhiro; Yoshimuta, Shigeharu*; Shiozawa, Shusaku; Fujikawa, Seigo; Tanaka, Toshiyuki; *; *; *

IAEA-TECDOC-1043, p.177 - 189, 1998/09

no abstracts in English

Journal Articles

High temperature gas-cooled reactor

Hagiwara, Masaki; Shigemoto, Masamitsu; Fujikawa, Seigo

Genshiryoku Nenkan '98/'99-Nen Ban, p.166 - 170, 1998/00

no abstracts in English

Journal Articles

Present status of the High Temperature engineering Test Reactor (HTTR)

Tanaka, Toshiyuki; Okubo, Minoru; Fujikawa, Seigo; Mogi, Haruyoshi; Suzuki, Hiroshi

Proc. of PBNC'98, 2, p.1203 - 1210, 1998/00

no abstracts in English

Journal Articles

Present status of the High Temperature engineering Test Reactor(HTTR)

Tanaka, Toshiyuki; Shiozawa, Shusaku; Okubo, Minoru; Fujikawa, Seigo; Mogi, Haruyoshi; Suzuki, Hiroshi

Proceedings of European Nuclear Conference (ENC'98), 4, 5 Pages, 1998/00

no abstracts in English

Journal Articles

Decommissioning of nuclear ship Mutsu

Fujikawa, Seigo; Kitamura, Toshikatsu; *; *; *; *

Techno Marine, 0(797), p.853 - 857, 1995/11

no abstracts in English

Journal Articles

Wake of nuclear ship Mutsu, present status of R & D and future plan, Part II; Design of N.S.Mutsu

Yamaki, Jikei; Fujikawa, Seigo; ; Ishida, Toshihisa; Mizushima, Toshihiko; *; Sakamoto, Yukio;

Genshiryoku Kogyo, 38(4), p.13 - 28, 1992/04

no abstracts in English

14 (Records 1-14 displayed on this page)
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