Steady and Transient Thermodynamic Performance Analysis of UN-FeCrAl Fuel Element under High Burnup

He Liang; Qiu Bowen; Wu Zhouzhi; Zhang Kun; Chen Ping; Gao Shixin; Hu chao; Xing Shuo; Fan Hang; Wang Yanpei

doi:10.13832/j.jnpe.2022.06.0227

Volume 43 Issue 6

Dec. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(6): 227-231

He Liang, Qiu Bowen, Wu Zhouzhi, Zhang Kun, Chen Ping, Gao Shixin, Hu chao, Xing Shuo, Fan Hang, Wang Yanpei. Steady and Transient Thermodynamic Performance Analysis of UN-FeCrAl Fuel Element under High Burnup[J]. Nuclear Power Engineering, 2022, 43(6): 227-231. doi: 10.13832/j.jnpe.2022.06.0227

Citation:

He Liang, Qiu Bowen, Wu Zhouzhi, Zhang Kun, Chen Ping, Gao Shixin, Hu chao, Xing Shuo, Fan Hang, Wang Yanpei. Steady and Transient Thermodynamic Performance Analysis of UN-FeCrAl Fuel Element under High Burnup[J]. Nuclear Power Engineering, 2022, 43(6): 227-231. doi: 10.13832/j.jnpe.2022.06.0227

Citation:

He Liang, Qiu Bowen, Wu Zhouzhi, Zhang Kun, Chen Ping, Gao Shixin, Hu chao, Xing Shuo, Fan Hang, Wang Yanpei. Steady and Transient Thermodynamic Performance Analysis of UN-FeCrAl Fuel Element under High Burnup[J]. Nuclear Power Engineering, 2022, 43(6): 227-231. doi: 10.13832/j.jnpe.2022.06.0227

PDF( 2333 KB)

Steady and Transient Thermodynamic Performance Analysis of UN-FeCrAl Fuel Element under High Burnup

doi: 10.13832/j.jnpe.2022.06.0227

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2022-07-21
Rev Recd Date: 2022-08-25
Publish Date: 2022-12-14

Abstract

Abstract

The UN-FeCrAl fuel element is one of the main schemes for high burnup application of accident tolerant fuel, and the thermodynamic property of the fuel element under high burnup needs to be evaluated. The steady and transient thermodynamic property of UN-FeCrAl fuel element under 68000 MW·d·t⁻¹(U) was predicted by FUPAC software, and the analysis results showed there is a good thermodynamic property of UN-FeCrAl fuel element under steady condition. Under transient conditions, the maximum pellet center temperature of UN fuel is only 862℃, which can meet the requirements of pellet temperature design, but the maximum transient stress of FeCrAl cladding will reach 459 MPa, and the transient strain will increase by 0.23% compared with steady-state strain, which may make FeCrAl cladding face the risk of transient stress and transient strain criterion exceeding the limit. Therefore, the subsequent research shall focus on the transient stress and transient strain of FeCrAl cladding.
- Accident tolerant fuel,
- UN fuel,
- FeCrAl cladding,
- Thermodynamic property

FullText(HTML)

References(12)

References

[1]	涂腾,李文杰,李伟,等. UN燃料性能数值分析[J]. 核动力工程,2017, 38(6): 185-188. doi: 10.13832/j.jnpe.2017.06.0185
[2]	SWEET R T, GEORGE N M, MALDONADO G I, et al. Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation[J]. Nuclear Engineering and Design, 2018, 328: 10-26.
[3]	邢硕,张坤,陈平,等. 燃料棒性能分析程序FUPAC V2.0的研发与验证[J]. 原子能科学技术,2021, 55(11): 2048-2053. doi: 10.7538/yzk.2020.youxian.0925
[4]	HAYES S L, THOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: III. Transport properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 289-299. doi: 10.1016/0022-3115(90)90376-X
[5]	STORMS E K. An equation which describes fission gas release from UN reactor fuel[J]. Journal of Nuclear Materials, 1988, 158: 119-129. doi: 10.1016/0022-3115(88)90161-4
[6]	ROSS S B, EL-GENK M S, MATTHEWS R B. Uranium nitride fuel swelling correlations[J]. Journal of Nuclear Materials, 1990, 170(2): 169-177.
[7]	SWEET R, GEORGE N M, TERRANI K A, et al. BISON fuel performance analysis of FeCrAl cladding with updated properties: TM-2016/475[R]. Oak Ridge: Oak Ridge National Laboratory, 2016.
[8]	HAYES S L, THOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: I. Physical properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 262-270. doi: 10.1016/0022-3115(90)90374-V
[9]	HAYES S L, THOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: II. Mechanical properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 271-288. doi: 10.1016/0022-3115(90)90375-W
[10]	HAYES S L, THOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: IV. Thermodynamic properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 300-318. doi: 10.1016/0022-3115(90)90377-Y
[11]	WU X, KOZLOWSKI T, HALES J D. Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions[J]. Annals of Nuclear Energy, 2015, 85: 763-775. doi: 10.1016/j.anucene.2015.06.032
[12]	雷阳,张海生,毛建军,等. 中子辐照对耐事故燃料FeCrAl合金力学性能的影响研究[J]. 核动力工程,2022, 43(1): 97-101.