A review of the development of nuclear fuel performance analysis and codes for PWRs. (1st December 2021)
- Record Type:
- Journal Article
- Title:
- A review of the development of nuclear fuel performance analysis and codes for PWRs. (1st December 2021)
- Main Title:
- A review of the development of nuclear fuel performance analysis and codes for PWRs
- Authors:
- Ding, Ming
Zhou, Xuhua
Zhang, Haojie
Bian, Haozhi
Yan, Qiang - Abstract:
- Highlights: Detailed description on the governing equations and key physical phenomena in the fuel pellet and cladding are summarized. Mature and next generation fuel performance analysis codes are concluded. Multi-physic coupled analysis codes are focused for the fuel performance analysis. Especially, the physical process and key phenomena are concluded during LOCA, RIA and severe accidents. Abstract: Nuclear fuel performance analysis is fundamental for the design of pressurized water reactors (PWRs) with great safety concerns. The analysis of a fuel rod involves many complex processes, including heat transfer, mechanics, material, mass transfer and chemistry interaction. This paper reviews the basic frame and recent progress of fuel performance analysis of PWRs during normal operation and accidents. Three conservation governing equations of heat, momentum and mass transfer, and the solution strategies are mentioned first. Reviewed phenomena include gas gap heat transfer, fission gas release, fuel pellet relocation, pellet cladding mechanical and chemical interactions, waterside corrosion, etc. Tools used to execute the performance analysis, namely, fuel performance analysis codes, are divided into mature and next generation codes and typical codes are also reviewed. FRAPCON/FRAPTRAN and FROBA are introduced as two representatives of mature generation codes, and BISON, ALCYONE and CAMPUS are reviewed as the representatives of the developing generation codes. The fuelHighlights: Detailed description on the governing equations and key physical phenomena in the fuel pellet and cladding are summarized. Mature and next generation fuel performance analysis codes are concluded. Multi-physic coupled analysis codes are focused for the fuel performance analysis. Especially, the physical process and key phenomena are concluded during LOCA, RIA and severe accidents. Abstract: Nuclear fuel performance analysis is fundamental for the design of pressurized water reactors (PWRs) with great safety concerns. The analysis of a fuel rod involves many complex processes, including heat transfer, mechanics, material, mass transfer and chemistry interaction. This paper reviews the basic frame and recent progress of fuel performance analysis of PWRs during normal operation and accidents. Three conservation governing equations of heat, momentum and mass transfer, and the solution strategies are mentioned first. Reviewed phenomena include gas gap heat transfer, fission gas release, fuel pellet relocation, pellet cladding mechanical and chemical interactions, waterside corrosion, etc. Tools used to execute the performance analysis, namely, fuel performance analysis codes, are divided into mature and next generation codes and typical codes are also reviewed. FRAPCON/FRAPTRAN and FROBA are introduced as two representatives of mature generation codes, and BISON, ALCYONE and CAMPUS are reviewed as the representatives of the developing generation codes. The fuel performance analysis in design-basis and severe accidents are also extensively reviewed as a new developing topic of fuel performance analysis, particularly in severe accidents. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 163(2021)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 163(2021)
- Issue Display:
- Volume 163, Issue 2021 (2021)
- Year:
- 2021
- Volume:
- 163
- Issue:
- 2021
- Issue Sort Value:
- 2021-0163-2021-0000
- Page Start:
- Page End:
- Publication Date:
- 2021-12-01
- Subjects:
- Fuel performance analysis -- BISON -- FRAPCON -- Thermal-mechanic-chemical coupled analysis -- Design basis accidents -- Severe accident
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2021.108542 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 18490.xml