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燃料棒性能分析软件JASMINE中裂变气体释放模型的评估
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Abstract:
裂变气体释放是燃料棒堆内安全运行必须考虑的关键行为。为了准确预测燃料棒中裂变气体释放行为，基于燃料棒性能分析软件JASMINE，集成了经典的Forsberg-Massih模型，并开发了两阶段裂变气体释放模型JASGAS，考虑晶界气泡重溶效应的影响，释放前后阶段的晶粒内部和晶界气体浓度变化。利用核燃料试验项目测量数据对模型进行评估，验证了模型的有效性。结果表明：在稳态工况下，JASGAS裂变气体释放模型预测较为准确，偏差较小；瞬态工况下，预测稍有偏低。
The fission gas release (FGR) is a crucial phenomenon, necessarily taken into account in the in-pile operation of the fuel rod. In order to predict accurately the fission gas release behavior of the fuel rod, based on the fuel rod performance analysis code JASMINE, incorporated the Forsberg-Massih model, and a two-stage FGR model, named JASGAS, was developed. The JASGAS model considers the grain boundary resolution effect, and the gas concentration variations inside the grain and at the grain boundary before and after the release. Some experimental data from fuel rod test project was used to evaluate the FGR models. The comparison results show that the JASGAS model predicts well under the steady-state conditions, and slightly under-predict under the transient conditions.
| [1] | Olander, D.R. (1976) Fundamental Aspects of Nuclear Reactor Fuel Elements. Technical Information Center-Energy Re-search and Development Administration, University of California, Berkeley. https://doi.org/10.2172/7343826 |
| [2] | Losonen, P. (2000) On the Behavior of Intragranular Fission Gas in UO2 Fuel. Journal of Nuclear Materials, 280, 56-72. https://doi.org/10.1016/S0022-3115(00)00028-3 |
| [3] | Booth, A.H. (1957) A Method of Calculating Fission Gas Diffusion from UO2 Fuel and Its Application to the X-2-f Loop Test. Rap-port Atomic Energy of Canada Limited CRDC-712. |
| [4] | Speight, M.V. (1969) A Calculation on the Migration of Fis-sion Gas in Material Exhibiting Precipitation and Re-Solution of Gas Atoms under Irradiation. Nuclear Science and En-gineering, 37, 180-185.
https://doi.org/10.13182/NSE69-A20676 |
| [5] | Forsberg, K. and Massih, A.R. (1985) Diffusion Theory of Fission Gas Migration in Irradiated Nuclear Fuel UO2. Journal of Nuclear Materials, 135, 140-148. https://doi.org/10.1016/0022-3115(85)90071-6 |
| [6] | Pastore, G., Luzzi, L., Di Marcello, V. and Van Uffelen, P. (2013) Physics-Based Modelling of Fission Gas Swelling and Release in UO2 Applied to Integral Fuel Rod Analysis. Nuclear Engineering and Design, 256, 75-86.
https://doi.org/10.1016/j.nucengdes.2012.12.002 |
| [7] | 崔羿, 丁淑蓉, 赵云妹, 等. 考虑晶界扩散和晶界联合的UO2燃料裂变气体模型[J]. 核动力工程, 2012(S2): 9-12+42. |
| [8] | Geelhood, K.J., Luscher, W.G., Beyer, C.E., et al. (2015) FRAPCON-4.0: A Computer Code for the Calculation of Steady-State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup. Pacific Northwest National Laboratory, United States. |
| [9] | Hales, J.D., Williamson, R.L., Novascone, S.R., et al. (2016) BISON Theory Manual, the Equations Behind Nuclear Fuel Analysis. Idaho National Laboratory, United States. https://doi.org/10.2172/1374503 |
| [10] | Rashid, Y., Dunham, R. and Montgomery, R. (2004) Fuel Analysis and Licensing Code: FALCON MOD01: Volume 1: Theoretical and Numerical Bases. EPRI, Palo Alto. |
| [11] | Turnbull, J.A. (1974) The Effect of Grain Size on the Swelling and Gas Release Properties of UO2 During Irradiation. Journal of Nuclear Materials, 50, 62-68. https://doi.org/10.1016/0022-3115(74)90061-0 |
| [12] | Hermansson, P. and Massih, A.R. (2002) An Effective Meth-od for Calculation of Diffusive Flow in Spherical Grain. Journal of Nuclear Materials, 304, 204-211. https://doi.org/10.1016/S0022-3115(02)00873-5 |
| [13] | Dowling, D.M., White, R.J. and Tucker, M.O. (1982) The Effect of Irradiation-Induced Re-Solution on Fission Gas Release. Journal of Nuclear Material, 110, 37-46. https://doi.org/10.1016/0022-3115(82)90405-6 |
