CTOD-based acceptance criteria for heat exchanger head staybolts
- 1. Westinghouse Savannah River Co., Aiken, SC (United States). Savannah River Technology Center
Description
The primary coolant piping system of the Savannah River Site (SRS) reactors contains twelve heat exchangers to remove the waste heat from the nuclear materials production. A large break at the inlet or outlet heads of the heat exchangers would occur if the restraint members of the heads become inactive. The heat exchanger head is attached to the tubesheet by 84 staybolts. The structural integrity of the heads is demonstrated by showing the redundant capacity of the staybolts to restrain the head at design conditions and under seismic loadings. The heat exchanger head is analyzed with a three-dimensional finite element model. The restraint provided by the staybolts is evaluated for several postulated cases of inactive or missing staybolts, that is, bolts that have a flaw exceeding the ultrasonic testing (UT) threshold depth of 25% of the bolt diameter. A limit of 6 inactive staybolts is reached with a fracture criterion based on the maximum allowable local displacement at the active staybolts which corresponds to the crack tip opening displacement (CTOD) of 0.032 inches. An acceptance criteria methodology has been developed to disposition flaws reported in the staybolt inspections while ensuring adequate restraint capacity of the staybolts to maintain integrity of the heat exchanger heads against collapse. The methodology includes an approach for the baseline and periodic inspections of the staybolts. A total of up to 6 staybolts, reported as containing flaws with depths at or exceeding 25%, would be acceptable in the heat exchanger
Additional details
Additional titles
- Augmented title (English)
- Crack tip opening displacement
Publishing Information
- Publisher
- American Society of Mechanical Engineers (ASME).
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0637-5
- Imprint Title
- 2nd ASME-JSME international conference on nuclear engineering -- 1993
- Imprint Pagination
- 914 p.
- Journal Page Range
- p. 107-116.
Conference
- Title
- 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
- Dates
- 21-24 Mar 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058972
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FASTENERS; FRACTURE MECHANICS; HEAT EXCHANGERS; IN-SERVICE INSPECTION; PRIMARY COOLANT CIRCUITS; RECOMMENDATIONS; RELIABILITY; RESTRAINTS; SAVANNAH RIVER PLANT; SEISMIC EFFECTS; SPECIAL PRODUCTION REACTORS
- Descriptors DEC
- COOLING SYSTEMS; INSPECTION; MECHANICS; NATIONAL ORGANIZATIONS; PRODUCTION REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-930352--.