Approach for improvement of maintenance technology of BMI
- 1. Mitsubishi Heavy Industries, Ltd., Tokyo (Japan)
- 2. Kansai Electric Power Co., Inc., Osaka (Japan)
Description
Primary water stress corrosion cracking (PWSCC) has been concerned in Bottom Mounted Instrumentation (BMI) of Reactor Pressure Vessel with alloy 600 for the last two decades. Generally the Rules on Fitness for Service for Nuclear Power Plants of JSME are applied for flaw evaluation after detecting defects in the operating nuclear plants. However in the case that a crack is detected in a complex configuration area such as J-groove weld, it is needed to perform a fracture mechanics approach using FE analysis because of different geometry and stress field from piping or vessels. The core support structure guidelines of JANSI have been revised to apply FE analysis for calculation of a precise stress intensity factor K of J-groove weld of BMI. The revision includes the notices of FE modeling, used material and K calculation method. The summary of this guideline is introduced in this paper. (author)
Additional details
Additional titles
- Original title (Japanese)
- Nippon hozen gakkai dai-10-kai gakujutsu koenkai yoshishu
Publishing Information
- Imprint Title
- Proceedings of the 10th annual meeting of Japan Society of Maintenology
- Imprint Pagination
- 750 p.
- Journal Page Range
- p. 610-612
Conference
- Title
- 10. annual meeting of Japan Society of Maintenology
- Dates
- 24-26 Jul 2013
- Place
- Suita, Osaka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 46064471
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- APPROPRIATE TECHNOLOGY; CRACKS; FINITE ELEMENT METHOD; INCONEL 600; MAINTENANCE; NUCLEAR POWER PLANTS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR INSTRUMENTATION; STRESS CORROSION; WATER; WELDED JOINTS
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; CALCULATION METHODS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CONTAINERS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; INCONEL ALLOYS; IRON ALLOYS; JOINTS; MATERIALS; MATHEMATICAL SOLUTIONS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NUCLEAR FACILITIES; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs., 2 figs. Imprint:Nippon hozen gakkai dai-10-kai gakujutsu koenkai yoshishu