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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

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

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

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