Published 1995
| Version v1
Book
Valve maintenance guideline to prevent thermal fatigue damage of the reactor pressure boundary piping
Creators
- 1. Mitsubishi Heavy Industries, Ltd., Kobe, Hyogo (Japan). Kobe Shipyard and Machinery Works
Description
Low temperature water flow through leaking stop valves into reactor pressure boundary mixes with hot cavity flow in the branch piping, and causes thermal cycles at the mixing portion. The safety injection piping of Farley Unit 2 suffered fatigue damage by the thermal cycles. To prevent this type of damage, it is important to understand the dependency of the thermal cycle characteristics on the leak flow rate through valves, and to maintain the flow rate enough below the critical value in view of the fatigue limit of the material. These were experimentally assessed, and the maintenance guideline of the valves to prevent the pipings damage was discussed
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1344-4
- Imprint Title
- International pressure vessels and piping codes and standards. Volume 2: Current perspectives; PVP-Volume 313-2
- Imprint Pagination
- 505 p.
- Journal Page Range
- p. 95-102.
Conference
- Title
- Joint ASME/JSME pressure vessels and piping conference.
- Dates
- 23-27 Jul 1995.
- Place
- Honolulu, HI (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27015601
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ENGINEERED SAFETY SYSTEMS; EXPERIMENTAL DATA; FARLEY-2 REACTOR; LEAKS; MAINTENANCE; MITIGATION; PIPES; SAFETY INJECTION; THERMAL FATIGUE; VALVES; WELDED JOINTS
- Descriptors DEC
- CONTROL EQUIPMENT; DATA; ENRICHED URANIUM REACTORS; EQUIPMENT; FATIGUE; FLOW REGULATORS; INFORMATION; JOINTS; MECHANICAL PROPERTIES; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-950740--.