Summary of the PISC III capability studies on wrought and cast austenitic steel welds

Conference · Fri Dec 01 04:00:00 EST 1995

OSTI ID:129201

Lemaitre, P; Koble, T D ^[1]; Doctor, S R ^[2]

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1. European Commission, Petten (Netherlands). Joint Research Centre
2. Pacific Northwest Lab., Richland, WA (United States)

In 1986 the Committee for the Safety of Nuclear Installations (CSNI) discussed the list of actions of the third phase of the Programme for the Inspection of Steel Components (PISC III) and proposed Action 4 on austenitic steel testing. Within the framework of Action 4 of the PISC III, three capability studies on stainless steel welds have been conducted. The first capability study used a series of 6 wrought-to-wrought stainless steel assemblies that contained a number of flaws such as intergranular stress corrosion cracks, mechanical and thermal fatigue cracks and PISC type A flaws. The second capability study used three cast-to-cast austenitic steel assemblies that contained lack of fusion flaws, mechanical fatigue cracks and PISC type A flaws. The third capability study used two wrought-to-cast austenitic steel assemblies that contained lack of fusion flaws and PISC type A flaws. In total more than 25 teams from 10 different countries participated. A lot of information was obtained on the performance of the inspection techniques used with respect to detection, false calls, depth and length sizing. Different flaw categories were considered to identify those difficult to detect. Furthermore an analysis at the level of techniques was performed which identified some of the more effective techniques and procedures. In this paper the main conclusions from these capability studies on austenitic steel welds will be discussed.

• DOE Contract Number: AC06-76RL01830
• OSTI ID: 129201
• Report Number(s): CONF-950740--; ISBN 0-7918-1348-7
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
AUSTENITIC STEELS
BWR TYPE REACTORS
CRACKS
IN-SERVICE INSPECTION
NONDESTRUCTIVE TESTING
PERFORMANCE
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
WELDED JOINTS