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JAEA Reports

Examination applied for the ruptured pipe at the Hamaoka Nuclear Power Station unit-1

Department of Hot Laboratories

JAERI-Tech 2002-050, 51 Pages, 2002/06

JAERI-Tech-2002-050.pdf:18.17MB

In Hamaoka Nuclear Power Station Unit-1 of Chubu Electric Power Company, a steam leak accident occurred with a pipe rupture. In order to investigate root cause of the pipe rupture, a task force was established within the Nuclear and Industrial Safety Agency (NISA). The JAERI was asked from NISA to cooperate as an independent neutral organization with NISA and perform an examination of the ruptured pipe. The JAERI examination group was formed at the Tokai Research Establishment and conducted some examinations of samples. In Dept. of Hot Laboratories, in order to respond the request of the investigation, the detailed program, various apparatuses, and technical staffs for the examinations are prepared. In this report, technical items in terms of contents of the examination, the used apparatuses, and techniques in three facilities in Dept. of Hot Laboratories (RFEF, RHL, and WASTEF) are summarized.

JAEA Reports

Data Book of Examination of the Ruptured Pipe at the Hamaoka Nuclear Power Station Unit-1

JAERI Working Group for Examination of the Ruptured Pipe at Hamaoka-1

JAERI-Tech 2002-045, 253 Pages, 2002/03

JAERI-Tech-2002-045.pdf:60.08MB

no abstracts in English

JAEA Reports

Report of examination of the ruptured pipe at the Hamaoka Nuclear Power Station Unit-1

JAERI Working Group for Examination of the Ruptured Pipe at Hamaoka-1

JAERI-Tech 2001-094, 60 Pages, 2001/12

JAERI-Tech-2001-094.pdf:13.99MB

no abstracts in English

Journal Articles

Evaluation method of performance of siphon break value as core covering system for water-cooled test and research reactors

; Kumada, Hiroaki; Kaminaga, Fumito*

Nihon Genshiryoku Gakkai-Shi, 42(4), p.325 - 333, 2000/04

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

no abstracts in English

Journal Articles

Thermohydraulic experiments on a water jet into vacuum during ingress of coolant event in a fusion experimental reactor

Ogawa, Masuro; Kunugi, Tomoaki

Fusion Engineering and Design, 29, p.233 - 237, 1995/00

 Times Cited Count:9 Percentile:66.51(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Visualization of buoyancy-driven exchange flow between helium and air through a small opening

*; *; *; *; Fumizawa, Motoo

The 4th Triennial Int. Symp. on Fluid Control,Fluid Measurement,and Visualization; FLUCOME 94, 0, p.691 - 695, 1994/00

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

JAEA Reports

Pipe Rupture Test Results; 6 inch Pipe Whip Test Under BWR LOCA Conditions -Overhang Length Parameter

; ; Ueda, Shuzo; ; ; ;

JAERI-M 83-020, 44 Pages, 1983/02

JAERI-M-83-020.pdf:1.7MB

no abstracts in English

Journal Articles

Resulto of 4 inch pipe whip tests under BWR LOCA conditions; Effects of clearance

Ueda, Shuzo; ; ; ; ; ; *

Nihon Genshiryoku Gakkai-Shi, 25(5), p.383 - 393, 1983/00

 Times Cited Count:1 Percentile:22.57(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Test Results of a Jet Impingement from a 4 Inch Pipe under BWR LOCA Conditions

; ; ; ; ; Ueda, Shuzo;

JAERI-M 82-110, 51 Pages, 1982/09

JAERI-M-82-110.pdf:1.53MB

no abstracts in English

JAEA Reports

JAEA Reports

Preliminary Analysis for Pipe Whip Test; RUN No.5319

; *

JAERI-M 8487, 34 Pages, 1979/10

JAERI-M-8487.pdf:0.9MB

no abstracts in English

14 (Records 1-14 displayed on this page)
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