Study on the Diffusion and Release Characteristics of Fission Products from TRISO Coated Fuel Particles
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摘要: 为研究三结构各向同性(TRISO)燃料颗粒裂变产物扩散释放特性,建立了辐照-热-力耦合作用下TRISO包覆燃料颗粒裂变产物Fick扩散模型,并通过IAEA CRP-6基准题进行了验证;利用所建模型对高温气冷堆典型工况下TRISO包覆燃料颗粒的性能进行了分析,同时,考虑裂变产物的反冲效应和热扩散效应,对TRISO包覆燃料颗粒不同温度及颗粒功率下裂变产物释放特性进行了分析。研究结果表明,高温会使TRISO包覆燃料颗粒裂变产物包容能力丧失,功率的提升则对裂变产物的释放影响较小。
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关键词:
- 三结构各向同性(TRISO) /
- 裂变产物扩散释放 /
- 多物理场耦合
Abstract: To analyze the diffusion and release characteristics of TRISO-coated fuel particles fission products, the Fick diffusion model of fission products of TRISO-coated fuel particles under irradiation-heat-force coupling is established and verified by the IAEA CRP-6 benchmark task. Then the performance of TRISO-coated fuel particles under typical working conditions of a high-temperature gas-cooled reactor is also analyzed by using the model. At the same time, the release characteristics of fission products at different temperatures and particle powers of TRISO-coated fuel particle are analyzed considering the recoil effect and thermal diffusion effect of fission products. The results show that high temperature causes the loss of the fission product containment capacity of TRISO-coated fuel particles, and the increase of power has less impact on the release of fission products. -
表 1 燃料芯核外的铀含量
Table 1. Uranium Content outside the Fuel Kernel
结构 铀质量分数/% Buffer 0.1 IPyC 0.01 SiC 0.0001 OPyC 0.0001 Matrix 0.00001 Kernel 99.88979 表 2 本研究结果与CRP-6参与者报告数值范围比较
Table 2. Comparison of the Range of Values Reported by CRP-6 Participants to This Study Results
核素 算例 ATLAS BISON* COPA FRESCO-II GETTER PARFUME 本研究 137Cs Case 1a 0.472 0.466 0.473 0.456 0.498 0.467 0.468 Case 1b 1.000 1.000 1.000 1.000 1.000 1.000 1.000 Case 4a 2.55×10-4 2.44×10-4 8.25×10-4 1.47×10-3 1.64×10-4 4.10×10-4 2.04×10-4 Case 4b 0.20 0.20 0.21 0.22 0.21 0.23 0.20 Case 5a 3.78×10-12 2.45×10-18 1.92×10-11 2.19×10-19 6.45×10-14 5.49×10-14 Case 5b 6.44×10-4 1.49×10-4 6.63×10-4 1.22×10-3 3.07×10-4 2.25×10-4 110Agm Case 4a 0.27 0.38 0.55 0.41 0.42 0.43 0.52 Case 4b 0.58 0.78 0.95 0.87 0.88 0.89 0.73 Case 5a 1.57×10-5 6.51×10-6 1.25×10-5 5.55×10-6 5.06×10-5 5.55×10-6 Case 5b 0.14 0.40 0.54 0.39 0.42 0.453 注:*BISON程序验证数据见文献[10] -
[1] HALES J D, WILLIAMSON R L, NOVASCONE S R, et al. Multidimensional multiphysics simulation of TRISO particle fuel[J]. Journal of Nuclear Materials, 2013, 443(1-3): 531-543. doi: 10.1016/j.jnucmat.2013.07.070 [2] IAEA. Advances in high temperature gas cooled reactor fuel technology: IAEA-TECDOC-CD-1674[R]. Vienna: International Atomic Energy Agency, 2013. [3] 陈平,李伟,李垣明,等. TRISO燃料颗粒三维多物理场耦合计算模型开发[J]. 核动力工程,2017, 38(5): 169-174. [4] 唐昌兵,李文杰,陈平,等. FCM燃料辐照-热-力耦合性能数值研究[J]. 核动力工程,2017, 38(S2): 16-19. [5] ZHANG C, WU Y W, LIU S C, et al. Multidimensional multiphysics modeling of TRISO particle fuel with SiC/ZrC coating using modified fission gas release model[J]. Annals of Nuclear Energy, 2020, 145: 107599. doi: 10.1016/j.anucene.2020.107599 [6] ZHANG C, WU Y W, HE Y N, et al. Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel[J]. Journal of Nuclear Materials, 2021, 556: 153171. doi: 10.1016/j.jnucmat.2021.153171 [7] IAEA. Fuel performance and fission product Behaviour in gas cooled reactors: IAEA-TECDOC-978[R]. Vienna: International Atomic Energy Agency, 1997. [8] SKERJANC W F, DEMKOWICZ P A. PARFUME theory and model basis report: INL/EXT-08-14497-Rev001[R]. Idaho Falls: Idaho National Lab. , 2018. [9] KONINGS R J M, ALLEN T R, STOLLER R E, et al. Comprehensive nuclear materials[M]. Amsterdam: Elsevier, 2012 [10] HALES J D, JIANG W, TOPTAN A, et al. Modeling fission product diffusion in TRISO fuel particles with BISON[J]. Journal of Nuclear Materials, 2021, 548: 152840. doi: 10.1016/j.jnucmat.2021.152840 [11] OLANDER D R. Fundamental aspects of nuclear reactor fuel elements: TID--26711-P1[R]. Vienna: IAEA, 1976. [12] PETTI D, MARTIN P, PHELIP M, et al. Development of improved models and designs for coated-particle gas reactor fuels -- final report under the international nuclear energy research initiative (I-NERI): INEEL/EXT-05-02615[R]. Idaho Falls: Idaho National Lab. , 2004.