Study on the Effects of Accident Tolerant Fuels on the Safety of CPR1000 Nuclear Power Plants

Liu Pingping; Liu Mengying; Xu Haode

doi:10.13832/j.jnpe.2024.06.0098

Volume 45 Issue 6

Dec. 2024

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2024 > 45(6): 98-105

Liu Pingping, Liu Mengying, Xu Haode. Study on the Effects of Accident Tolerant Fuels on the Safety of CPR1000 Nuclear Power Plants[J]. Nuclear Power Engineering, 2024, 45(6): 98-105. doi: 10.13832/j.jnpe.2024.06.0098

Citation:

Liu Pingping, Liu Mengying, Xu Haode. Study on the Effects of Accident Tolerant Fuels on the Safety of CPR1000 Nuclear Power Plants[J]. Nuclear Power Engineering, 2024, 45(6): 98-105. doi: 10.13832/j.jnpe.2024.06.0098

Citation:

PDF( 6278 KB)

Study on the Effects of Accident Tolerant Fuels on the Safety of CPR1000 Nuclear Power Plants

doi: 10.13832/j.jnpe.2024.06.0098

China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, 518000, China

Received Date: 2024-02-26
Rev Recd Date: 2024-04-08
Publish Date: 2024-12-17

Abstract

Abstract

In this paper, CPR1000 is taken as the reference unit. According to the Level 1 CPR1000 Probabilistic Safety Analysis (PSA) results, the Large Break LOCA, Intermediate Break LOCA, Small Break LOCA, Station Blackout (SBO), Total Loss of Feedwater (TLOFW) and Anticipated Transient without Trip (ATWT) with Loss of Main Feedwater (LOMF) are selected as the representative design extend condition (DEC) accident scenarios. Using LOCUST and SPRUCE, the thermal and hydraulic codes developed by China Nuclear Power Technology Research Institute Co., Ltd. based on the performance of accident tolerant fuel (ATF), deterministic calculations are carried out for the five types of ATF under development, namely, ATF-1, ATF-2, ATF-3, ATF-4, and ATF-5. Compared with the traditional UO₂-Zr material, the accident process, core damage time, system success criteria and personnel response time of different ATFs under the above typical accidents are analyzed. It is found that the lower peak cladding temperature and higher cladding limit temperature of ATF in the accident make CPR1000 unit have greater safety margin, which provides support for ATF material selection. Based on the results of deterministic analysis, the Level 1 PSA model is established for different ATF, and the influence of different ATF materials on the safety of CPR1000 unit is given from the perspective of probability theory. The results show that there is no substantial benefit from the direct application of existing ATF to existing reactors. Based on the deterministic and probabilistic analyses, the development direction of reactor based on ATF is given in this paper.
- Design extend condition,
- Accident tolerant fuel,
- Deterministic analysis,
- Probabilistic analysis,
- Future reactors

FullText(HTML)

References(9)

References

[1]	OTT L J, ROBB K R, WANG D. Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions[J]. Journal of Nuclear Materials, 2014, 448(1-3): 520-533. doi: 10.1016/j.jnucmat.2013.09.052
[2]	YAMAMOTO Y, PINT B A, TERRANI K A, et al. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors[J]. Journal of Nuclear Materials, 2015, 467: 703-716. doi: 10.1016/j.jnucmat.2015.10.019
[3]	CARPENTER D M. An assessment of silicon carbide as a cladding material for light water reactors[D]. Cambridge: Massachusetts Institute of Technology, 2010.
[4]	TERRANI K A, WANG D A, OTT L J, et al. The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents[J]. Journal of Nuclear Materials, 2014, 448(1-3): 512-519. doi: 10.1016/j.jnucmat.2013.09.051
[5]	LATTA R, REVANKAR S T, SOLOMON A A. Modeling and measurement of thermal properties of ceramic composite fuel for light water reactors[J]. Heat Transfer Engineering, 2008, 29(4): 357-365. doi: 10.1080/01457630701825390
[6]	WU X L, LI W, WANG Y, et al. Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions[J]. Annals of Nuclear Energy, 2015, 80: 1-13.
[7]	吴和鑫,金德升,苟军利,等. 卡轴事故下事故容错燃料对核反应堆安全潜在影响分析[J]. 核动力工程,2023, 44(S1): 75-80.
[8]	徐涛,黄俊,张斌,等. 针对压水堆核电厂全厂断电事故的事故容错燃料性能分析[C]//第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集. 荣成: 中国核学会核能动力分会反应堆热工流体专业委员会,中核核反应堆热工水力技术重点实验室,2017.
[9]	Mengying Liu, YunLei, Zhaojie Tan, Pingping Liu. The Effect on PSV success criteria of Accident Tolerant Fuel during LOFW ATWS[C]. The 17th International Topic Meeting on Nuclear Reactor Thermal Hydraulics. New York: Association for Computing Machinery, 2017.