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JAEA Reports

Fracture mechanics analysis and evaluation for the RPV of chinese Qinshan 300MW NPP under PTS

He, Y.; Isozaki, Toshikuni

JAERI-Research 2000-012, p.58 - 0, 2000/03

JAERI-Research-2000-012.pdf:1.89MB

no abstracts in English

JAEA Reports

Crack extension analysis under pressurized thermal shock loading by ADINA

Isozaki, Toshikuni; Shibata, Katsuyuki; *; *

JAERI-Research 96-039, 133 Pages, 1996/07

JAERI-Research-96-039.pdf:3.85MB

no abstracts in English

JAEA Reports

Journal Articles

Influence of wetting effect at the outer surface of the pipe on increase in leak rate; Experimental results and discussion

Isozaki, Toshikuni; Shibata, Katsuyuki

LBB95: Specialist Meeting on Leak Before Break in Reactor Piping and Vessels, 0, 10 Pages, 1995/00

no abstracts in English

Journal Articles

Results of reliability test program on light water reactor piping

Shibata, Katsuyuki; Isozaki, Toshikuni; Ueda, Shuzo; Kurihara, Ryoichi; Onizawa, Kunio; Kosaka, Atsuo

Nucl. Eng. Des., 153, p.71 - 86, 1994/00

 Times Cited Count:11 Percentile:69.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Overview of reliability test program on primary coolant piping of light water reactors

Shibata, Katsuyuki; Isozaki, Toshikuni; Ueda, Shuzo; Kurihara, Ryoichi; Onizawa, Kunio; Kosaka, Atsuo

Nihon Genshiryoku Gakkai-Shi, 35(10), p.923 - 939, 1993/10

 Times Cited Count:1 Percentile:18.76(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Results of piping reliability test program at JAERI

Shibata, Katsuyuki; Isozaki, Toshikuni; *; Kurihara, Ryoichi; Onizawa, Kunio; Kosaka, Atsuo

Proc. of 6th German-Japanese Seminar on Structural Strength and NDE Problems in Nuclear Engineering, 19 Pages, 1993/00

no abstracts in English

Journal Articles

Overview of piping reliability test program at the Japan Atomic Energy Research Institute

Isozaki, Toshikuni; Shibata, Katsuyuki; *; Ueda, Shuzo; Kurihara, Ryoichi

Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology, Vol. SDO, p.401 - 412, 1991/08

no abstracts in English

Journal Articles

Structural analysis of Japanese PWR steel containment vessel under internal pressure loading

Isozaki, Toshikuni; Soda, Kunihisa; Miyazono, S.

Nucl. Eng. Des., 126, p.387 - 393, 1991/00

 Times Cited Count:3 Percentile:40.83(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of leak analysis programs from through-wall crack

; Shibata, Katsuyuki; Isozaki, Toshikuni

JAERI-M 90-050, 106 Pages, 1990/03

JAERI-M-90-050.pdf:2.17MB

no abstracts in English

Journal Articles

Measurement of leak-rate through fatigue-cracks in pipes under four-point bending and BWR conditions

Isozaki, Toshikuni; Shibata, Katsuyuki; ; *

Int. J. Press. Vessels Piping, 43, p.399 - 411, 1990/00

 Times Cited Count:8 Percentile:75.98(Engineering, Multidisciplinary)

no abstracts in English

Journal Articles

Structural analysis of Japanese PWR steel containment under inner pressure loading

Isozaki, Toshikuni; Soda, Kunihisa; Miyazono, S.

NUREG-CP-0095, p.523 - 536, 1988/11

no abstracts in English

JAEA Reports

Study on the jet flow in primary coolant system pipe rupture of a light water reactor

Isozaki, Toshikuni

JAERI-M 88-077, 106 Pages, 1988/04

JAERI-M-88-077.pdf:4.18MB

no abstracts in English

JAEA Reports

Estimation of leak rates through a through-wall cracked pipes using Moody's critical flow model

; Shibata, Katsuyuki; Isozaki, Toshikuni; Onizawa, Kunio

JAERI-M 88-039, 38 Pages, 1988/03

JAERI-M-88-039.pdf:0.76MB

no abstracts in English

Journal Articles

Temperature increase on target due to jet impingement under BWR/PWR loss of coolant accident conditions

Isozaki, Toshikuni; Miyazono, S.

Nucl. Eng. Des., 106, p.257 - 263, 1988/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Pipe rupture accident on Surry Nuclear Power Plant

Miyazono, S.; Ueda, Shuzo; Shibata, Katsuyuki; Isozaki, Toshikuni; Onizawa, Kunio; ; Kurihara, Ryoichi; *;

Nihon Genshiryoku Gakkai-Shi, 29(11), p.952 - 969, 1987/11

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Pipe rupture test results: Cross-over leg pipe whip test under PWR LOCA conditions (RUN 5808,5809)

Kurihara, Ryoichi; Ueda, Shuzo; Isozaki, Toshikuni; ; ; Miyazono, S.

JAERI-M 87-135, 43 Pages, 1987/09

JAERI-M-87-135.pdf:2.06MB

no abstracts in English

JAEA Reports

Evaluation of leak rate by EPRI code

Isozaki, Toshikuni; *; ; Miyazono, S.

JAERI-M 87-121, 32 Pages, 1987/08

JAERI-M-87-121.pdf:0.81MB

no abstracts in English

18 (Records 1-18 displayed on this page)
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