Published October 1986
| Version v1
Journal article
Provisions to prevent strain-induced corrosion cracking in ferritic piping systems of boiling water reactors
- 1. Kraftwerk Union A.G., Erlangen (Germany, F.R.)
Description
Based on failure analysis and evaluations of laboratory test results, system areas are localized which are to be regarded as susceptible to strain-induced corrosion cracking (SICC). Possible systems engineering, operational, design and manufacturing provisions for preventing SICC are described. Necessary measures have already been taken by BWR operators, acting in part together with authorised experts and licensing authorities, in the case of plants which are in operation. (orig.)
Additional details
Additional titles
- Augmented title (English)
- KWV series 69 and 72 BWR
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 96
- Journal Issue
- 2/3
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 217-224
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 11. MPA-seminar on safety and availability in plant engineering especially in nuclear power plant engineering.
- Dates
- 10-11 Oct 1985.
- Place
- Stuttgart (Germany, F.R.).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 18012859
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CORROSION PROTECTION; CRACK PROPAGATION; CRACKS; FERRITIC STEELS; LOW ALLOY STEELS; NUCLEAR POWER PLANTS; PIPES; REACTOR COMPONENTS; STEAM LINES; STRESS CORROSION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; NUCLEAR FACILITIES; PIPELINES; POWER PLANTS; POWER REACTORS; REACTORS; STEELS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS