Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating. (15th September 2022)
- Record Type:
- Journal Article
- Title:
- Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating. (15th September 2022)
- Main Title:
- Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating
- Authors:
- Jeong, Eun
Jo, Yunki
Shin, ChangHwan
Yang, Yong-Sik
Kim, Jae-Yong
Lee, Deokjung - Abstract:
- Highlights: Performance analysis of a commercial pressurized water reactor core loaded with accident-tolerant fuel. Development of accident-tolerant fuel containing Mo/Cr metallic microcell UO2 pellets and a CrAl coating on the cladding. The metallic microcell UO2 pellet can increase the thermal conductivity of fuel pellets. Systematic reactor core performance and safety analysis of the reactor core with accident-tolerant fuels from a neutronic perspective. Abstract: This paper presents a performance analysis of a commercial pressurized water reactor (PWR) core loaded with accident-tolerant fuel (ATF) containing Mo/Cr metallic microcell UO2 pellets and a CrAl coating on the cladding. Metallic microcell UO2 pellets using additive materials, such as Mo and Cr, with coated cladding have been developed by the Korea Atomic Energy Research Institute (KAERI) for an OPR-1000 reactor. As demonstrated by the fuel pellet developed at KAERI, a metallic microcell UO2 pellet can increase the thermal conductivity of fuel pellets by forming a metallic film that encapsulates the UO2 to connect the metallic microcell and UO2 pellets; however, there has been no systematic core performance and safety analysis of the core with ATFs. In this study, core analysis with ATFs was conducted from a neutronic perspective. 1) The fuel assembly (FA) containing Mo/Cr metallic microcell UO2 pellets was analyzed using the lattice code STREAM developed by Ulsan National Institute of Science and Technology inHighlights: Performance analysis of a commercial pressurized water reactor core loaded with accident-tolerant fuel. Development of accident-tolerant fuel containing Mo/Cr metallic microcell UO2 pellets and a CrAl coating on the cladding. The metallic microcell UO2 pellet can increase the thermal conductivity of fuel pellets. Systematic reactor core performance and safety analysis of the reactor core with accident-tolerant fuels from a neutronic perspective. Abstract: This paper presents a performance analysis of a commercial pressurized water reactor (PWR) core loaded with accident-tolerant fuel (ATF) containing Mo/Cr metallic microcell UO2 pellets and a CrAl coating on the cladding. Metallic microcell UO2 pellets using additive materials, such as Mo and Cr, with coated cladding have been developed by the Korea Atomic Energy Research Institute (KAERI) for an OPR-1000 reactor. As demonstrated by the fuel pellet developed at KAERI, a metallic microcell UO2 pellet can increase the thermal conductivity of fuel pellets by forming a metallic film that encapsulates the UO2 to connect the metallic microcell and UO2 pellets; however, there has been no systematic core performance and safety analysis of the core with ATFs. In this study, core analysis with ATFs was conducted from a neutronic perspective. 1) The fuel assembly (FA) containing Mo/Cr metallic microcell UO2 pellets was analyzed using the lattice code STREAM developed by Ulsan National Institute of Science and Technology in terms of the Mo depletion chain and the impact of resonance treatment. 2) The initial and equilibrium cores were analyzed using STREAM/RAST-K 2.0 with respect to the impact of the additives and CrAl coating on the cycle length, power peaking, and fuel temperatures, etc. The reductions in the equilibrium core cycle length were 61, 44, and 65 effective full power days for each material type. 3) Finally, a rod ejection accident (REA) analysis was performed on the core using a Mo metallic microcell UO2 pellet and CrAl-coated ATF. Moreover, the maximum fuel centerline temperature of the ATF core was determined to be approximately 200 ℃ lower than that of the reference UO2 core. Furthermore, the presence of additional thermal margins in ATF cores for steady-state and accident transient scenarios was verified through a systematic neutronic analysis, and future studies will focus on the optimization of the ATF-loaded core by exploiting the extra margins achieved by ATFs and increasing the cycle length. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 175(2022)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 175(2022)
- Issue Display:
- Volume 175, Issue 2022 (2022)
- Year:
- 2022
- Volume:
- 175
- Issue:
- 2022
- Issue Sort Value:
- 2022-0175-2022-0000
- Page Start:
- Page End:
- Publication Date:
- 2022-09-15
- Subjects:
- Accident-Tolerant Fuel -- Mo/Cr Metallic Microcell UO2 Pellets -- CrAl Coating -- Systematic core performance and safety analysis -- Lattice code STREAM -- Resonance treatment -- STREAM/RAST-K 2.0 -- Rod ejection accident (REA) -- Thermal margin
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.2022.109217 ↗
- 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:
- 22348.xml