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Journal Articles

Effect of cooling conditions on fuel failure during fast and slow power transients

Sobajima, Makoto; Katanishi, Shoji

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.249 - 254, 1991/00

no abstracts in English

Journal Articles

Results of the power-up test of the nuclear-powered ship MUTSU and test programs of her experimental voyages

; Ishida, Toshihisa; ; Sakamoto, Yukio; Kyoya, Masahiko;

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.515 - 526, 1991/00

no abstracts in English

Journal Articles

Hydrogen generation during cladding/coolant interactions under reactivity initiated accident conditions

Fuketa, Toyoshi;

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.271 - 277, 1991/00

no abstracts in English

Journal Articles

PWR cold-leg small break LOCA with faulty HPI; Effect of break area and intentional system depressurization

Kumamaru, Hiroshige; Kukita, Yutaka

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.203 - 208, 1991/00

no abstracts in English

Journal Articles

Application of new coolant inventory tracking method to PWR small break LOCA simulation experiments at ROSA-IV/LSTF

Suzuki, Mitsuhiro

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.311 - 317, 1991/00

no abstracts in English

Journal Articles

Improved graphite damage model for predicting property changes of HTGR graphites under isothermal and nonisothermal irradiations

; H.Cords*; H.Nickel*

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.553 - 558, 1991/00

no abstracts in English

Journal Articles

Determination of hot spot factors for thermal and hydraulic design of High Temperature Engineering Test Reactor (HTTR)

Maruyama, So; Murakami, Tomoyuki*; Fujii, Sadao*; Fujimoto, Nozomu; Tanaka, Toshiyuki; Sudo, Yukio; Saito, Shinzo

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.425 - 430, 1991/00

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

Journal Articles

A New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Kaminaga, Masanori; Sudo, Yukio

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.73 - 79, 1991/00

no abstracts in English

Journal Articles

Fundamental study on thermo-hydraulic phenomena concerning to passive safety of advanced marine reactor

*; *; *; *; *; Akino, Norio; Takeda, Tetsuaki; *

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.101 - 107, 1991/00

no abstracts in English

Journal Articles

Transient analysis of loss of feed water at PIUS experimental apparatus

Watanabe, Tadashi; Asahi, Yoshiro; *; Anoda, Yoshinari; *; Kukita, Yutaka

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.315 - 320, 1991/00

no abstracts in English

Journal Articles

Measurement of transient elongation of a fuel rod under reactivity initiated accident conditions and preliminary analysis

Ishijima, Kiyomi; Nakamura, Takehiko

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.263 - 270, 1991/00

no abstracts in English

Journal Articles

Underwater cutting of JPDR reactor pressure vessel and core internals

Tachibana, Mitsuo; Hoshi, Tatsuo;

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.81 - 84, 1991/00

no abstracts in English

Journal Articles

Thermal transient analysis for structural integrity of high temperature components in HTTR

Hada, Kazuhiko; Fujimoto, Nozomu; Sudo, Yukio; Wada, Hozumi*

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.291 - 298, 1991/00

no abstracts in English

Journal Articles

Safety analysis of reactivity abnormal events in the HTTR

Nakagawa, Shigeaki; Sawa, Kazuhiro; Ohashi, Kazutaka*

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.299 - 304, 1991/00

no abstracts in English

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