Analyses and solutions for the inlet pipeline crack of primary system pipe dead end check valve of Qinshan nuclear power plant
Creators
- 1. CNNC Nuclear Power Operations Management Co., Ltd., Haiyan (China)
Description
A number of pipe dead ends exist in the primary system of nuclear power plants, pipe dead end equipments and pipelines easy to produce defects that seriously affect the safety of system operation, analysis and solution researching for this problem is an important work of plants aging management. There is a typical pipe dead end in the primary system of hot injection pipeline in Qinshan nuclear power plant, the defects of check valve internal leakage and inlet pipeline cracks are bring forward as example to analyze the steam interspaces producing principles, influence to the SCC corrosion of materials, and the solutions that replacing partial pipeline based on the aging management was proposed with some reference for the further researching of pipe dead end and replacing work of the main loop pressure boundary equipment. (authors)
Additional details
Publishing Information
- Publisher
- China Nuclear Physics Society
- Imprint Place
- Beijing (China)
- ISBN
- 978-7-5022-6126-9
- Imprint Title
- Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.4--nuclear material sub-volume
- Imprint Pagination
- 375 p.
- Journal Page Range
- p. 6-11
Conference
- Title
- 2013 academic annual meeting of China Nuclear Society
- Dates
- 10-14 Sep 2013
- Place
- Harbin (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48055714
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; CRACKS; DEFECTS; MANAGEMENT; NUCLEAR POWER PLANTS; PIPELINES; PRIMARY COOLANT CIRCUITS; QINSHAN-1 REACTOR; SAFETY; VALVES
- Descriptors DEC
- CHEMICAL REACTIONS; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 figs., 4 refs.