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JAEA Reports

Study on temperature coefficients of reactivity for pebble bed type HTGRs loaded with highly $$^{239}$$Pu-enriched plutonium

*; Yamashita, Kiyonobu; Shindo, Ryuichi; Fujimoto, Nozomu

JAERI-Tech 96-025, 50 Pages, 1996/06

JAERI-Tech-96-025.pdf:1.3MB

no abstracts in English

Journal Articles

Nuclear design of the high-temperature engineering test reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; Fujimoto, Nozomu; Takeda, Takeshi

Nuclear Science and Engineering, 122, p.212 - 228, 1996/00

 Times Cited Count:22 Percentile:85.94(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Importance determination method for geometry splitting with Russian roulette in Monte Carlo calculations of thick and complicated core shielding structure

Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku

Journal of Nuclear Science and Technology, 32(10), p.971 - 980, 1995/10

 Times Cited Count:1 Percentile:18.1(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Neutron response analysis of wide range detector in High Temperature Engineering Test Reactor (HTTR)

Murata, Isao; Yamashita, Kiyonobu; Shindo, Ryuichi; Shiozawa, Shusaku; *

JAERI-Tech 95-036, 101 Pages, 1995/07

JAERI-Tech-95-036.pdf:2.46MB

no abstracts in English

JAEA Reports

Design of High Temperature Engineering Test Reactor (HTTR)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shindo, Masami; Shiozawa, Shusaku; Mogi, Haruyoshi; Okubo, Minoru; Ito, Noboru; Shindo, Ryuichi; et al.

JAERI 1332, 247 Pages, 1994/09

JAERI-1332.pdf:11.53MB

no abstracts in English

Journal Articles

Prediction of nongaseous fission products behavior in the primary cooling system of high temperature gas-cooled reactor

Sawa, Kazuhiro; Murata, Isao; Saikusa, Akio; Shindo, Ryuichi; Shiozawa, Shusaku; Baba, Osamu

Journal of Nuclear Science and Technology, 31(7), p.654 - 661, 1994/07

 Times Cited Count:2 Percentile:28.77(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of control rod reactivity worths for AVR power plant at cold and hot conditions

Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi; *; H.Werner*

Journal of Nuclear Science and Technology, 31(5), p.470 - 478, 1994/05

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of local power distribution with fine-mesh core model for High Temperature Engineering Test Reactor(HTTR)

Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*

Journal of Nuclear Science and Technology, 31(1), p.62 - 72, 1994/01

 Times Cited Count:3 Percentile:36.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Destruction of weapons-grade plutonium with pebble bed type HTGRs using burner balls and breeder balls

Yamashita, Kiyonobu; *; Shindo, Ryuichi; Murata, Isao; Saikusa, Akio

Nihon Genshiryoku Gakkai-Shi, 36(9), p.865 - 868, 1994/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Reactor shielding design of the High Temperature Engineering Test Reactor; Design analysis and shielding characteristics

Shindo, Ryuichi; Murata, Isao; Sawa, Kazuhiro; Shiozawa, Shusaku; *; Mori, Tomoaki*

Proc. of the 8th Int. Conf. on Radiation Shielding, p.351 - 358, 1994/00

no abstracts in English

Journal Articles

Reactor shielding design of the High Temperature Engineering Test Reactor; Analysis of radiation streaming through the standpipes by Monte Carlo code MCNP

Murata, Isao; Shindo, Ryuichi; *; *; *

Proc. of the 8th Int. Conf. on Radiation Shielding, p.359 - 364, 1994/00

no abstracts in English

Journal Articles

Reactor shielding design of the High Temperature Engineering Test Reactor; Application of 3-dimensional Monte Carlo code MCNP to shielding analysis for thick and complicated structure

Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku

Proc. of the 8th Int. Conf. on Radiation Shielding, p.365 - 370, 1994/00

no abstracts in English

Journal Articles

Effects of core models and neutron energy group structures on xenon oscillation in large graphite-moderated reactors

Yamashita, Kiyonobu; Harada, Hiro; Murata, Isao; Shindo, Ryuichi; *

Journal of Nuclear Science and Technology, 30(3), p.249 - 260, 1993/03

 Times Cited Count:1 Percentile:19.22(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Characteristic and subject on the use of plutonium

Shindo, Ryuichi

Enerugi, Shigen, 14(5), p.419 - 423, 1993/00

no abstracts in English

Journal Articles

Optimization of power distribution to achieve outlet gas-coolant temperature of 950$$^{circ}$$C for HTTR

Yamashita, Kiyonobu; Maruyama, So; Murata, Isao; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*; *

Journal of Nuclear Science and Technology, 29(5), p.472 - 481, 1992/05

no abstracts in English

Journal Articles

Analysis of overall temperature coefficient of reactivity of the VHTRC-1 core with a nuclear design code system for the High-Temperature Engineering Test Reactor

Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi

Nuclear Science and Engineering, 110, p.177 - 185, 1992/02

 Times Cited Count:3 Percentile:54.12(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Evaluation of fission product sources for shielding design of HTTR

Sawa, Kazuhiro; Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku

JAERI-M 91-198, 58 Pages, 1991/11

JAERI-M-91-198.pdf:1.58MB

no abstracts in English

JAEA Reports

Evaluation of shut down margin in scram condition for High Temperature Engineering Test Reactor(HTTR)

Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Fujimoto, Nozomu; Shindo, Ryuichi; Sudo, Yukio

JAERI-M 91-165, 71 Pages, 1991/10

JAERI-M-91-165.pdf:1.94MB

no abstracts in English

Journal Articles

Evaluation of local power distribution with fine-mesh core model for the HTTR

Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.413 - 418, 1991/00

no abstracts in English

Journal Articles

Optimization of power distribution to achieve outlet gas-coolant temperature of 950$$^{circ}$$C for High Temperature Engineering Test Reactor(HTTR)

Yamashita, Kiyonobu; Maruyama, So; Murata, Isao; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*; *

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.419 - 424, 1991/00

no abstracts in English

30 (Records 1-20 displayed on this page)