Citation: | Ye Yaoxin, Fu Pengtao. Study on Prediction and Diagnosis of Fuel Rod Break Size during Degassing Operation of PWR[J]. Nuclear Power Engineering, 2024, 45(6): 220-225. doi: 10.13832/j.jnpe.2024.06.0220 |
[1] |
International Atomic Energy Agency. Fuel failure in water reactors: causes and mitigation: IAEA-TECDOC-1345[R]. Vienna: IAEA, 2003.
|
[2] |
International Atomic Energy Agency. Review of fuel failures in water cooled reactors: No. NF-T-2.5[R]. Vienna: IAEA, 2010.
|
[3] |
International Atomic Energy Agency. Fuel failure in normal operation of water reactors: experience, causes and mitigation: IAEA-TECDOC-2004[R]. Vienna: IAEA, 2022.
|
[4] |
LEWIS B J, CHAN P K, EL-JABY A, et al. Fission product release modelling for application of fuel-failure monitoring and detection-an overview[J]. Journal of Nuclear Materials, 2017, 489: 64-83. doi: 10.1016/j.jnucmat.2017.03.037
|
[5] |
EL-JABY A, LEWIS B J, THOMPSON W T, et al. A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis[J]. Journal of Nuclear Materials, 2010, 399(1): 87-100. doi: 10.1016/j.jnucmat.2010.01.006
|
[6] |
FU P T, LIANG S, LU S B, et al. Relationship between fuel reliability and I-131/I-133 in the primary coolant of CPR1000 PWRs[J]. Frontiers in Energy Research, 2022, 10: 860480. doi: 10.3389/fenrg.2022.860480
|
[7] |
李兰,杨洪润. 压水堆核电厂燃料元件破损诊断方法[J]. 核动力工程,2008, 29(4): 135-139.
|
[8] |
MENENDEZ M A T. Fuel failure detection, characterization and modelling: effect on radionuclide behaviour in PWR primary coolant[D]. Essonne: Université de Paris-Sud, 2009.
|
[9] |
KLEVINSKAS G, JUODIS L, PLUKIENĖ R, et al. Analysis of iodine release from the defective fuel elements of the RBMK-1500 reactor[J]. Lithuanian Journal of Physics, 2007, 47(2): 211-219. doi: 10.3952/lithjphys.47208
|
[10] |
肖维,尹楚轩,李宏轩,等. 基于人工神经网络的压水堆燃料破损状态监测[J]. 原子能科学技术,2020, 54(3): 481-487. doi: 10.7538/yzk.2019.youxian.0258
|
[11] |
BOOTH A H. A method of calculating fission gas diffusion from UO2 fuel and its application to the X-2-f loop test[Z]. Chalk River Project: Atomic Energy of Canada Ltd, 1957.
|
[12] |
CHUN M H, TAK N I, LEE S K. Development of a computer code to estimate the fuel rod failure using primary coolant activities of operating PWRS[J]. Annals of Nuclear Energy, 1998, 25(10): 753-763. doi: 10.1016/S0306-4549(97)00126-6
|
[13] |
LEWIS B J. Fission product release from nuclear fuel by recoil and knockout[J]. Journal of Nuclear Materials, 1987, 148(1): 28-42. doi: 10.1016/0022-3115(87)90515-0
|