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Search Results: Records 1-14 displayed on this page of 14
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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

https://doi.org/10.1016/0029-5493(91)90027-F
 Times Cited Count：3 Percentile：41.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Ductile crack growth analysis of surface cracked plate in tension using three-dimensional FEM

Onizawa, Kunio; Ueda, Shuzo; Miyazono, S.; *

Advances in Fracture and Fatigue for the 1990s, Vol. II, p.1 - 6, 1989/00

no abstracts in English

Journal Articles

Evaluation of JAERIs ductile pipe fracture test results on stainless steel and carbon steel piping

Shibata, Katsuyuki; *; Onizawa, Kunio; Miyazono, S.

Nucl. Eng. Des., 111, p.135 - 145, 1989/00

https://doi.org/10.1016/0029-5493(89)90285-9
 Times Cited Count：6 Percentile：60.1(Nuclear Science & Technology)

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

Ductile fracture behavior of 3-inch diameter carbon steel piping with a circumferential through-wall crack under bending load

; Shibata, Katsuyuki; Onizawa, Kunio; ; Oba, Toshihiro; Miyazono, S.

JAERI-M 88-130, 120 Pages, 1988/07

JAERI-M-88-130.pdf:3.45MB

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

https://doi.org/10.1016/0029-5493(88)90282-8
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress and evaluation of test results on JAERIs ductile pipe fracture test program

Shibata, Katsuyuki; *; Onizawa, Kunio; Miyazono, S.

Proc. on the 4th Japanese-German Joint Seminar on Structural Strength and NDE Programs in Nucl. Eng., p.347 - 364, 1988/00

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

https://doi.org/10.3327/jaesj.29.952
 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

JAEA Reports

Study on ductile unstable fracture of piping materials in light water reactor,3; Fracture behavior of through-wall or part-through cracked tension specimens machined from 24-inch diameter carbon steel pipe at room temperature

Onizawa, Kunio; Shibata, Katsuyuki; Yasuda, Yuji; Oba, Toshihiro; ; Miyazono, S.

JAERI-M 87-077, 83 Pages, 1987/06

JAERI-M-87-077.pdf:5.4MB

no abstracts in English

JAEA Reports

Investigation on ductile fracture behavior of 3-inch diameter type 304 stainless steel pipe with a circumferential through-wall crack

Yasuda, Yuji; Shibata, Katsuyuki; Onizawa, Kunio; ; Oba, Toshihiro; Miyazono, S.

JAERI-M 87-068, 111 Pages, 1987/05

JAERI-M-87-068.pdf:3.0MB

no abstracts in English

Journal Articles

Experimental and analytical studies of pipe whip tests under PWR LOCA conditions

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

Nucl. Eng. Des., 103, p.253 - 265, 1987/00

https://doi.org/10.1016/0029-5493(87)90309-8
 Times Cited Count：4 Percentile：45.24(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Investigation and evaluation of ductile fracture behaviors in LWR piping under bending load

Shibata, Katsuyuki; Yasuda, Yuji; Onizawa, Kunio; Miyazono, S.

Structural Mechanics in Reactor Technology,Vol.G, p.461 - 466, 1987/00

no abstracts in English

14 (Records 1-14 displayed on this page)
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