Evaluation of structural integrity and controllability of main feed water control valve for APWRS
- 1. Kobe Shipyard and Machinery Works, Mitsubishi Heavy Industries, Ltd. (Japan)
- 2. Takasago Research and Development Center, Mitsubishi Heavy Industries, Ltd. (Japan)
- 3. Mitsubishi Heavy Industries, Ltd. (Japan)
Description
In Pressurized Water Reactors (PWR), the main feed water control valve always controls the mass flow rate of main feed water to maintain the water level of steam generator within the allowable range. For the main feed water control valve of PWR, we have used an air operated globe valve conventionally since it has large capacity and quick responsibility. On the Advanced Pressurized Water Reactors (APWR) system conditions, the mass flow rate of main feed water increases compared with the conventional PWR system conditions as an increase of the generating power. So, it is expected that the fluid force will increase, and it could cause critical damage on internal parts of the valve, such as plug, stem, etc. and uncontrollability of the valve. In this study, we measured the stem strain in the fluid tests using scale model and test loop under the APWR feed water flow rate conditions. The stem strain gave the stem stress and the fluid force acting on the plug surface. We evaluated the stem integrity from the stem stress and confirmed the influence which the fluid force had on the valve controllability by simulating the feed water system considering the fluid force. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 7-5022-3400-4
- Imprint Title
- The 13th international conference on nuclear engineering abstracts
- Imprint Pagination
- 604 p.
- Journal Page Range
- p. 103
Conference
- Title
- 13. international conference on nuclear engineering
- Dates
- 16-20 May 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 38008234
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR; CAPACITY; CONTROL; DAMAGE; EVALUATION; FEEDWATER; FLOW RATE; PWR TYPE REACTORS; SCALE MODELS; SIMULATION; STEAM GENERATORS; STRAINS; STRESSES; SURFACES; VALVES
- Descriptors DEC
- BOILERS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FLUIDS; GASES; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS