Calculation of Stress Intensity Factor for Surface Cracks in FeCrAl Cladding under Force-Irradiation Coupling
-
摘要: 为研究高辐照剂量情况下铁素体FeCrAl包壳管对断裂失效破坏的抵抗能力,利用有限元方法结合Zencrack软件中的裂纹块分析技术,计算了内压和辐照肿胀应力耦合载荷作用下FeCrAl包壳管轴向半椭圆表面裂纹的裂尖应力强度因子。获得了不同辐照肿胀应变分布情况下内、外表面不同深度裂纹的裂尖应力强度因子变化规律,分析了辐照肿胀效应的影响作用。研究结果表明,相比于均匀辐照肿胀应变分布情况,包壳管在径向方向存在线性梯度变化的辐照肿胀应变时,内表面轴向半椭圆裂纹的裂尖应力强度因子水平显著降低,而外表面轴向半椭圆裂纹的裂尖应力强度因子水平显著提升。Abstract: In order to study the resistance of Ferritic FeCrAl alloy cladding to fracture failure under high radiation dose, the crack tip stress intensity factor of axial semi-elliptical surface crack of FeCrAl cladding tube under internal pressure and radiation swelling stress coupling load is calculated by finite element method combined with crack block analysis technique in Zencrack software. The change rule of stress intensity factor at crack tip with different depth on inner and outer surfaces under different radiation swelling strain distribution is obtained, and the influence of radiation swelling effect is analyzed. The results show that compared with the uniform radiation swelling strain distribution, when the radiation swelling strain of the cladding tube has a linear gradient in the radial direction, the crack tip stress intensity factor of the axial semi-elliptical crack on the inner surface decreases significantly. On the other hand, the crack tip stress intensity factor of the axial semi-elliptical crack on the outer surface increases significantly.
-
Key words:
- FeCrAl /
- Irradiation swelling /
- Stress intensity factor /
- Semi-elliptical axial crack
-
-
[1] 陈亮,宋小明,庞华,等. 柔度法计算Zr-4合金包壳管轴向裂纹应力强度因子的研究[J]. 核动力工程,2019, 40(5): 202-206. doi: 10.13832/j.jnpe.2019.05.0202 [2] 孙超,谭军,应诗浩,等. N18锆合金氢致裂纹延迟开裂临界温度研究[J]. 金属学报,2009, 45(5): 541-546. doi: 10.3321/j.issn:0412-1961.2009.05.005 [3] 汪秉忠,丁淑蓉,陈亮,等. 辐照蠕变对锆合金包壳管吸氢所致多场耦合行为的影响[J]. 原子能科学技术,2017, 51(9): 1625-1632. doi: 10.7538/yzk.2017.51.09.1625 [4] DUDAREV S L, MASON D R, TARLETON E, et al. A multi-scale model for stresses, strains and swelling of reactor components under irradiation[J]. Nuclear Fusion, 2018, 58(12): 126002. doi: 10.1088/1741-4326/aadb48 [5] REALI L, BOLEININGER M, GILBERT M R, et al. Macroscopic elastic stress and strain produced by irradiation[J]. Nuclear Fusion, 2022, 62(1): 016002. doi: 10.1088/1741-4326/ac35d4 [6] 涂腾,高士鑫,周毅,等. FeCrAl-UN燃料棒性能模拟分析[J]. 核动力工程,2021, 42(S2): 165-170. doi: 10.13832/j.jnpe.2021.S2.0165 [7] ZENCRACK. User's manual for 8.2[M]. London: Zentech International Ltd, 2017: 10-173. [8] THOMPSON Z T, TERRANI K A, YAMAMOTO Y. Elastic modulus measurement of ORNL ATF FeCrAl alloy:ORNL/TM-2015/632 AF5810000; NEAF278[R]. Oak Ridge: Oak Ridge National Lab, 2015. [9] 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. doi: 10.1016/j.nucengdes.2017.11.043