Failure cases of welds between pressure vessel nozzle and main pipe safe-end in high temperature water environments and relevant research
Creators
- 1. Shanghai Research Institute of Materials, Shanghai Key Lab for Engineering Materials Application and Evaluation, National Quality Supervision Testing Center for Metallic Materials (China)
Description
Background: A connection between a low alloy steel pressure vessel nozzle and a stainless steel main pipe safe-end in a pressurized water reactor (PWR) nuclear power plant is a dissimilar metal weld, which is at key location of pressure boundary and serves in high temperature primary water environments. Since 1990, cracking failure incidents happened on the welds in the primary water coolant of several PWRs in the countries such as USA, Sweden and Japan. Purpose: This paper is to briefly review the typical cases involving this problem in engineering and relevant researches. Methods: Methods such as nondestructive testing, crack and microstructure observation, finite element analysis were used in the failure analysis. Results: The cause of the failure cases was primary water stress corrosion cracking (PWSCC). Conclusions: It is concluded that the welds of 600 Alloy type such as 82/182 are susceptible to PWSCC but those of 690 Alloy Type such as 52/152 have excellent resistance to the cracking, and more researches are necessary. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Techniques
- Journal Volume
- 36
- Journal Issue
- 4
- Journal Page Range
- [6 p.]
- ISSN
- 0253-3219
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 47057393
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACKING; CRACKS; FAILURES; FINITE ELEMENT METHOD; LOW ALLOY STEELS; MICROSTRUCTURE; NICKEL BASE ALLOYS; NONDESTRUCTIVE TESTING; NUCLEAR POWER PLANTS; PIPE FITTINGS; PRESSURE VESSELS; PWR TYPE REACTORS; REVIEWS; STAINLESS STEELS; STRESS CORROSION; WATER; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; CHEMICAL REACTIONS; CONTAINERS; CORROSION; DECOMPOSITION; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MATERIALS TESTING; MATHEMATICAL SOLUTIONS; NICKEL ALLOYS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; PYROLYSIS; REACTORS; STEELS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Special Issue on Structural Mechanics in Reactor Technology; 1 figs., 17 refs., 040644-1-040644-6