Evaluation of leaking Alloy 600 nozzles and remaining life predictions for similar nozzles in PWR primary system applications
- 1. ABB Combustion Engineering Nuclear Operations, Windsor, CT (United States)
- 2. Arizona Public Service, Phoenix, AZ (United States)
Description
Since 1986, a number of PWR primary system instrumentation nozzles fabricated of forged Alloy 600 have developed throughwall defects resulting in primary coolant leakage. Several nozzles from various plants have been analyzed to establish failure modes, failure mechanisms and the relationships between the failures and metallurgical or fabrication factors. The results of these examinations indicate that the leaks resulted from throughwall IGSCC near the partial penetration attachment welds. The most probable mechanism was PWSCC with the welds being the sources of high residual tensile stresses that initiated and propagated the cracks. Failed nozzles had a variety of metallurgical characteristics and mechanical properties ranging from low yield strength, coarse grain material to high yield strength coarse grain material to high strength very fine grain material. There were no obvious manufacturing discrepancies noted that would have significantly increased the susceptibility of these nozzles to PWSCC. There are numerous Alloy 600 penetrations of the primary pressure boundary in a typical PWR and concerns developed about increased potential for leakage as plants age. Detected leakage could result in forced outages to repair or replace nozzles and undetected leakage could result in unacceptable corrosion of the low alloy steel components. An obvious need was a predictive model that could relate times-to-first failure to operating conditions, installation stresses and material properties and that could be used to access the effects of temperature changes and stress reductions on remaining lifetimes. Plant failure experience and laboratory test data were used along with a process that used statistics of extremes and Monte Carlo simulations to develop a predictive model for PWSCC. The process for developing the model, the characteristics of the model and the application of the model to a specific case are described
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1361-4
- Imprint Title
- Service experience and reliability improvement: Nuclear, fossil, and petrochemical plants. PVP-Volume 288
- Imprint Pagination
- 437 p.
- Journal Page Range
- p. 49-57.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26021919
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CRACK PROPAGATION; EXPERIMENTAL DATA; FAILURE MODE ANALYSIS; FORECASTING; INCONEL 600; INTERGRANULAR CORROSION; LEAKS; MATHEMATICAL MODELS; NOZZLES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR INSTRUMENTATION; REACTOR OPERATION; SERVICE LIFE; STRESS CORROSION; WELDED JOINTS
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CONTAINERS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DATA; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; INFORMATION; IRON ALLOYS; JOINTS; LIFETIME; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NUMERICAL DATA; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; TITANIUM ADDITIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.