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http://dx.doi.org/10.1016/j.net.2022.01.024

Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code  

Zhang, Bin (School of Nuclear Science and Technology, Xi'an Jiaotong University)
Gao, Pengcheng (School of Nuclear Science and Technology, Xi'an Jiaotong University)
Xu, Tao (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China)
Gui, Miao (School of Nuclear Science and Technology, Xi'an Jiaotong University)
Shan, Jianqiang (School of Nuclear Science and Technology, Xi'an Jiaotong University)
Publication Information
Nuclear Engineering and Technology / v.54, no.7, 2022 , pp. 2475-2490 More about this Journal
Abstract
The Accident Tolerant Fuel (ATF) is a new concept of fuel, which can not only withstand the consequences of the accident for a longer time, but also maintain or improve the performance under operating conditions. ISAA is a self-developed severe accident analysis code, which uses modular structures to simulate the development processes of severe accidents in nuclear plants. The basic version of ISAA is developed based on UO2-Zr fuel. To study the potential safety gain of ATF cladding, an improved version of ISAA, referred to as ISAA-ATF, is introduced to analyze the station blackout accident of PWR using ATF cladding. The results show that ATF cladding enable the core to maintain a longer time compared to zirconium alloy cladding, thereby enhancing the accident mitigation capability. Meanwhile, the generation of hydrogen is significantly reduced and delayed, which proves that ATF can improve the safety characteristics of the nuclear reactor.
Keywords
Accident Tolerant Fuel; New material cladding; ISAA-ATF; SBO accident;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
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1 Xiaoli Wu, Wei Li, Yang Wang, et al., Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions, Ann. Nucl. Energy 80 (2015) 1-13.   DOI
2 B.S. Li, Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels under Light Water Reactor Conditions, Dissertations & Theses, Gradworks, 2013.
3 D. Kim, H.-G. Lee, J.Y. Park, W.-J. Kim, Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications, J. Nucl. Mater. 458 (2015) 29-36.   DOI
4 Bo Jonsson, Qin Lu, Dilip Chandrasekaran, Roger Berglund, Fernando Rave, Oxidation and creep limited lifetime of Kanthal APMT®, a dispersion strengthened FeCrAlMo alloy designed for strength and oxidation resistance at high temperatures, Oxid Met 79 (2013) 29-39.   DOI
5 K.G. Field, S.A. Briggs, K. Sridharan, et al., Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys [J], J. Nucl. Mater. 489 (2017) 118-128, https://doi.org/10.1016/j.jnucmat.2017.03.038.   DOI
6 X. Wu, T. Kozlowski, J.D. Hales, Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions, Ann. Nucl. Energy 85 (2015) 763-775.   DOI
7 D. Chandramouli, S.T. Revankar, Development of thermal models and analysis of UO2-BeO fuel during a loss of coolant accident, Int. J. Nucl. Energy 2014 (2014).
8 Bin Zhang, Jian Deng, Maolin Jing, et al., A newly-developed suppression pool model based on ISAA code, Nucl. Sci. Eng. (2020), https://doi.org/10.1080/00295639.2020.1861862.   DOI
9 Jinyu Gao, Research on advanced investment in nuclear fuel in the UK, Nucl. Fuel Cycle 10 (2015) (in Chinese).
10 Wenchuan Xie, China General Nuclear Power Group Takes the Lead the Accident Tolerant Fuel Major Technology, 6, 2016, p. 25, edition 008.
11 Pengcheng Gao, Bin Zhang, et al., Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I: module verification and application in CAP1400, Ann. Nucl. Energy 3 (2021) 25, https://doi.org/10.1016/j.anucene.2021.108305.   DOI
12 Guoxin Du, Station Black-Out Severe Accident Analysis of a Typical 1000MWe PWR[D], Xi'an Jiaotong University, 2013.
13 L.J. Ott, K.R. Robb, D. Wang, Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions, J. Nucl. Mater. 448 (2014) 520-533.   DOI
14 L.J. Ott, K.R. Robb, Accident tolerant fuel/cladding: preliminary reactor DBDaccident simulations, in: The First ATF Workshop, 24-25 July, 2013.
15 Brad J. Merrill, Shannon M. Bragg-Sitton, SiC modifications to melcor for severe accident analysis applications[C], TopFuel (2013). Charlotte, North Carolina, September 15-19, 2013.
16 K.A. Terrani, L.L. Snead, J.C. Gehin, Microencapsulated fuel technology for commercial light water and advanced reactor application, J. Nucl. Mater. 427 (2012) 209-224.   DOI
17 L.L. Snead, T. Nozawa, Y. Katoh, et al., Handbook of SiC properties for fuel performance modeling, J. Nucl. Mater. 371 (1) (2007) 329-377.   DOI