United States criteria for repair and replacement of BWR piping and steam generator tubing
Creators
- 1. Nuclear Regulatory Commission, Washington, DC (USA). Office of Inspection and Enforcement
Description
The criteria currently used by the US Nuclear Regulatory Commission in dealing with repairs and replacement of BWR piping and steam generator tubing are discussed and the bases for these criteria are provided. As a result of extensive cracking in BWR pipes caused by intergranular stress corrosion, a program of augmented inspection and leak testing has been instituted. Emphasis is placed on returning such piping to original design conformance either by replacement with non-susceptible material or by a combination of stress improvement and environmental control. As a result of a number of degradation mechanisms in steam generator tubes, inspection and criteria for plugging or sleeving have been instituted along with broad recommendations aimed at an integrated program for resolving steam generator tube problems. (author)
Additional details
Publishing Information
- Journal Title
- Int. J. Press. Vessels Piping
- Journal Volume
- 25
- Journal Issue
- 1-4
- Series
- Int. J. Press. Vessels Piping.
- Journal Page Range
- 231-238
- ISSN
- 0308-0161
- CODEN
- PRVPA
Conference
- Title
- 4. International Seminar on Assuring Structural Integrity of Steel Reactor Pressure Boundary Components.
- Dates
- 26-27 Aug 1985.
- Place
- Ispra (Italy).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 18065791
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; INSPECTION; PIPES; REPAIR; STEAM GENERATORS; TUBES
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS