JPH056158B2 - - Google Patents

Info

Publication number
JPH056158B2
JPH056158B2 JP58071880A JP7188083A JPH056158B2 JP H056158 B2 JPH056158 B2 JP H056158B2 JP 58071880 A JP58071880 A JP 58071880A JP 7188083 A JP7188083 A JP 7188083A JP H056158 B2 JPH056158 B2 JP H056158B2
Authority
JP
Japan
Prior art keywords
straight pipe
cross
piping
reducer
section
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
JP58071880A
Other languages
English (en)
Japanese (ja)
Other versions
JPS5942497A (ja
Inventor
Koji Fujimoto
Isao Nemezawa
Wataru Sagawa
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP58071880A priority Critical patent/JPS5942497A/ja
Publication of JPS5942497A publication Critical patent/JPS5942497A/ja
Publication of JPH056158B2 publication Critical patent/JPH056158B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Pipeline Systems (AREA)
  • Investigating Or Analyzing Materials By The Use Of Ultrasonic Waves (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
JP58071880A 1983-04-22 1983-04-22 原子力プラントの配管系 Granted JPS5942497A (ja)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58071880A JPS5942497A (ja) 1983-04-22 1983-04-22 原子力プラントの配管系

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58071880A JPS5942497A (ja) 1983-04-22 1983-04-22 原子力プラントの配管系

Publications (2)

Publication Number Publication Date
JPS5942497A JPS5942497A (ja) 1984-03-09
JPH056158B2 true JPH056158B2 (enrdf_load_stackoverflow) 1993-01-25

Family

ID=13473271

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58071880A Granted JPS5942497A (ja) 1983-04-22 1983-04-22 原子力プラントの配管系

Country Status (1)

Country Link
JP (1) JPS5942497A (enrdf_load_stackoverflow)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS63212893A (ja) * 1987-03-02 1988-09-05 株式会社東芝 原子炉冷却材再循環系の配管

Also Published As

Publication number Publication date
JPS5942497A (ja) 1984-03-09

Similar Documents

Publication Publication Date Title
JP2005195596A (ja) 溶接部の割れを検出するための方法及び装置
CN113109451A (zh) 一种厚壁管道焊缝缺陷的在线检测装置及方法
CN108291894B (zh) 用于检查垫圈焊接部的方法、系统和固定装置
US5377237A (en) Method of inspecting repaired stub tubes in boiling water nuclear reactors
EP0453166B1 (en) Ultrasonic inspection of pump shafts
US20050199591A1 (en) Method of forming a weld pad
JPH056158B2 (enrdf_load_stackoverflow)
JPS5946597A (ja) 原子力プラントの配管系
Narabayashi et al. Experimental study on leak flow model through fatigue crack in pipe
Aakre et al. Welded Attachments and Hydrostatic Pressure Testing Rules for Diffusion Bonded Heat Exchangers
Edelmann Application of ultrasonic testing techniques on austenitic welds for fabrication and in-service inspection
JP3448222B2 (ja) 原子炉用のシュラウド
JPH0320050Y2 (enrdf_load_stackoverflow)
JPS6410799B2 (enrdf_load_stackoverflow)
Edelmann Ultrasonic examination of austenitic welds at reactor pressure vessels
Glass et al. Inspection and repair techniques and strategies for alloy 600 PWSCC in reactor vessel head CRD nozzles and welds
Kemppainen et al. Comparison of Realistic Artificial Cracks and In-Service Cracks.
Kuroishi et al. Guided wave pipe inspection and monitoring system
Cattant Thermal Fatigue Failure
AU2022206688A1 (en) Nozzle weld scanner saddle apparatus
FUJIMAKI et al. RELIABILITY TESTS FOR REACTOR INTERNALS XA0055988 REPLACEMENT TECHNOLOGY
JPS60141368A (ja) 水冷溶接法
WELDING Quality Control
Fujimaki et al. Reliability tests for reactor internals replacement technology
Doctor et al. Assessing primary water stress corrosion crack morphology and nondestructive evaluation reliability