Standard study of the technology and safety performance evaluation on Emergency Core Cooling System Strainer
Creators
Description
Emergency Core Cooling System (ECCS) strainer is the important equipment to ensure the effective and safe operation of ECCS, Containment Spray System (CSS) and the Cavity Injection System (CIS) etc. after PWR NPP accidents. Strainer equipment design technology, test technology and relevant core cooling safety evaluation technology are important design and research work of nuclear power projects, and also one of the important contents of nuclear safety review. In the past decades years, many countries have done a lot of research work in this field, and made great efforts to solve related nuclear safety issues. However, there is still a lack of a complete set of international standards to guide research, design and safety performance evaluation work related to ECCS strainer. Therefore, it is necessary to establish a set of standards covering the performance evaluation of ECCS strainer in accordance with the requirements of nuclear safety regulation, combined with the research results and engineering practices of NPPs owners. The standards can be the basis and reference for the nuclear regulatory authorities and the NPP owners to have unified standards to carry out nuclear safety work, greatly improving work efficiency and reducing unnecessary contradictions in nuclear safety review work. Based on the research results of the ECCS strainer and its nuclear safety performance evaluation and the nuclear engineering practice research conducted by the author, this paper proposes to establish a set of standards on ECCS strainer which covering debris source work down, upstream analysis, debris pressure drop test, chemical effect test, downstream effect (in-vessel) test and downstream effect (ex-vessel) analysis, and finally give out preliminary research results. Keywords: design and performance evaluation of Emergency Core Cooling System Strainer,; debris source; upstream analysis; debris head loss test. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs. Book of Abstracts
- Imprint Pagination
- 146 p.
- Journal Page Range
- p. 74-75
- Report number
- IAEA-CN--308
Conference
- Title
- Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Acronym
- International Conference on Topical Issues in Nuclear Installation Safety
- Dates
- 18-21 Oct 2022
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54004917
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SPRAY SYSTEMS; COOLING; ECCS; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; PERFORMANCE; PRESSURE DROP; PWR TYPE REACTORS; RADIATION PROTECTION; REACTOR ACCIDENTS; REACTOR DESIGN; REACTOR OPERATION; REGULATIONS; SAFETY ANALYSIS; SAFETY REPORTS; SAFETY STANDARDS
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; CONTAINMENT SYSTEMS; DESIGN; ENGINEERED SAFETY SYSTEMS; ENGINEERING; ENRICHED URANIUM REACTORS; LAWS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; POWER REACTORS; REACTOR LIFE CYCLE; REACTOR PROTECTION SYSTEMS; REACTORS; STANDARDS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-CN--308-118