[1]
|
Yang, J., Yang, Y., Deng, C., et al. (2019) Best Estimate plus Uncertainty Analysis of a Large Break LOCA on Genera-tion III Reactor with RELAP5. Annals of Nuclear Energy, 127, 326-340.
https://doi.org/10.1016/j.anucene.2018.12.019
|
[2]
|
Prošek, A. and Berar, O.A. (2012) Advanced Presentation of BETHSY 6.2 TC Test Results Calculated by RELAP5 and TRACE. Science and Technology of Nuclear Installations, 2012, Article ID: 812130.
https://doi.org/10.1155/2012/812130
|
[3]
|
Tran, V.P., Nguyen, K.C., Hartanto, D., et al. (2021) Development of a PARCS/Serpent Model for Neutronics Analysis of the Dalat Nuclear Research Reactor. Nuclear Science and Techniques, 32, 34-46.
https://doi.org/10.1007/s41365-021-00855-5
|
[4]
|
姜强, 刘天才, 杨宏伟. 基于UQLab的COBRA不确定性量化分析[J]. 科技创新导报, 2020, 17(5): 76-79.
|
[5]
|
Chauliac, C., Aragonés, J.M., Bestion, D., et al. (2011) NURESIM—A European Simulation Platform for Nuclear Reactor Safety: Multi-Scale and Multi-Physics Calculations, Sensitivity and Uncertainty Analysis. Nuclear Engineering Design, 241, 3416-3426. https://doi.org/10.1016/j.nucengdes.2010.09.040
|
[6]
|
Chanaron, B. (2017) Overview of the NURESAFE Europe-an Project. Nuclear Engineering and Design, 321, 1-7.
https://doi.org/10.1016/j.nucengdes.2017.09.001
|
[7]
|
Demazière, C., Sanchez-Espinoza, V.H. and Chanaron, B. (2020) Advanced Numerical Simulation and Modelling for Reactor Safety—Contributions from the CORTEX, HPMC, McSAFE and NURESAFE Projects. EPJ Nuclear Sciences & Technologies, 6, 42. https://doi.org/10.1051/epjn/2019006
|
[8]
|
Szilard, R., Zhang, H., Kothe, D., et al. (2011) The Consortium for Advanced Simulation of Light Water Reactors. Idaho National Lab. (INL), Idaho Falls.
|
[9]
|
Bradley, K. (2013) NEAMS: The Nuclear Energy Advanced Modeling and Simulation Program. Argonne National Lab. (ANL), Ar-gonne.
|
[10]
|
ARPA-E (2019) Generating Electricity Managed by Intelligent Nuclear Assets.
https://arpa-e.energy.gov/technologies/programs/gemina
|
[11]
|
杨文, 胡长军, 刘天才, 等. 数值反应堆及CVR1.0研究进展[J]. 原子能科学技术, 2019, 53(10): 1821.
|
[12]
|
贺青云, 陈俊, 马忠英, 等. 三维耦合分析软件的落棒事故分析[J]. 原子能科学技术, 2022, 56(2): 343-350.
|
[13]
|
张宏博, 赵晨, 彭星杰, 等. 数字化反应堆高保真中子学程序SHARK研发[J]. 原子能科学技术, 2022, 56(2): 334-342.
|
[14]
|
余红星, 李文杰, 柴晓明, 等. 数字反应堆发展与挑战[J]. 核动力工程, 2020, 41(4): 7.
|
[15]
|
曹良志, 邹晓阳, 刘宙宇, 等. 高保真数值核反应堆不确定度量化方法研究进展[J]. 核动力工程, 2021, 42(2): 1-15.
|
[16]
|
D’Auria, F.S., Glaeser, H., Lee, S., et al. (2008) Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series. IAEA.
|
[17]
|
杨文. 基于确定性采样的核热耦合计算不确定性分析[D]: [硕士学位论文]. 哈尔滨: 哈尔滨工程大学, 2020.
|
[18]
|
王洋洋. 核电厂典型事故分析不确定性评价方法研究[D]: [硕士学位论文]. 哈尔滨: 哈尔滨工程大学, 2017.
|
[19]
|
张春艳. 核数据不确定性传播方法研究[D]: [硕士学位论文]. 哈尔滨: 哈尔滨工程大学, 2016.
|
[20]
|
De Crècy, A. (1996) Determination of the Uncertainties of the Constitutive Relationships in the Calthare 2 Code. American Society of Me-chanical Engineers, New York.
|
[21]
|
Heo, J., Turinsky, P.J. and Doster, J.M. (2013) Optimization of Thermal-Hydraulic Reactor System for SMRs via Data Assimilation and Uncertainty Quantification. Nuclear Science Engineering, 173, 293-311.
https://doi.org/10.13182/NSE11-113
|
[22]
|
Petruzzi, A., Kovtonyuk, A., Raucci, M., et al. (2013) A Procedure for Characterizing the Range of Input Uncertainty Parameters by the Use of FFTBM. https://doi.org/10.1115/ICONE20-POWER2012-54025
|
[23]
|
Reventós, F., de Alfonso, A., Zhang, J., et al. (2016) Premium, a Benchmark on the Quantification of the Uncertainty of the Physical Models in the System Thermal-Hydraulic Codes: Methodologies and Data Review.
|
[24]
|
Zhang, J., Dethioux, A., Kovtonyuk, A., et al. (2019) Development of a Pragmatic Approach to Model Input Uncertainty Quantification for BEPU Applications. Nuclear Technology, 205, 140-152.
https://doi.org/10.1080/00295450.2018.1516055
|
[25]
|
Cabellos de Francisco, O.L., Martínez, J.S. and Diez de la Obra, C.J. (2011) Isotopic Uncertainty Assessment Due to Nuclear Data Uncertainties in High-Burnup Sam-ples.
|
[26]
|
Wieselquist, W., Vasiliev, A. and Ferroukhi, H. (2012) Nuclear Data Uncertainty Propagation in a Lattice Physics Code Using Stochastic Sampling. In: Proceedings of the PHYSOR-2012 Conference, Advances in Reactor Phys-ics Linking Research, Industry, and Education, on CD-ROM, American Nuclear Society, Knoxville, 15-20.
|
[27]
|
Williams, M., Wiarda, D., Smith, H., et al. (2012) Development of a Statistical Sampling Method for Un-certainty Analysis with SCALE. American Nuclear Society, Inc., La Grange Park.
|
[28]
|
Pusa, M. and Isotalo, A. (2017) Uncertainty Analysis of Assembly and Core-Level Calculations with Application to CASMO-4E and SIMULATE-3. Annals of Nuclear Energy, 104, 124-131.
https://doi.org/10.1016/j.anucene.2017.01.042
|
[29]
|
Garcia-Herranz, N., Cabellos, O., Sanz, J., et al. (2008) Propa-gation of Statistical and Nuclear Data Uncertainties in Monte Carlo Burn-Up Calculations. Annals of Nuclear Energy, 35, 714-730.
https://doi.org/10.1016/j.anucene.2007.07.022
|
[30]
|
Wan, C., Cao, L., Wu, H., et al. (2015) Code Development for Eigenvalue Total Sensitivity Analysis and Total Uncertainty Analysis. Annals of Nuclear Energy, 85, 788-797. https://doi.org/10.1016/j.anucene.2015.06.036
|
[31]
|
Ornl, S. (2011) A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design. ORNL/TM-2005/39, Version, 6(3).
|
[32]
|
Kodeli, I. (2001) Multidimen-sional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application. Nuclear Science and Engineering, 138, 45-66. https://doi.org/10.13182/NSE00-43
|
[33]
|
Han, T.Y., Lee, H.C. and Noh, J.M. (2015) Development of a Sensitivity and Uncertainty Analysis Code for High Temperature Gas-Cooled Reactor Physics Based on the Generalized Perturbation Theory. Annals of Nuclear Energy, 85, 501-511. https://doi.org/10.1016/j.anucene.2015.06.005
|
[34]
|
Pusa, M. (2012) Perturbation-Theory-Based Sensitivity and Uncertainty Analysis with CASMO-4. Science and Technology of Nuclear Installations, 2012, Article ID: 157029. https://doi.org/10.1155/2012/157029
|
[35]
|
Takeda, T., Asano, K. and Kitada, T. (2006) Sensitivity Analysis Based on Transport Theory. Journal of Nuclear Science and Technology, 43, 743-749. https://doi.org/10.1080/18811248.2006.9711156
|
[36]
|
刚直. 核截面引起积分参数keff不确定度的一维分析程序开发[D]: [硕士学位论文]. 北京: 中国原子能科学研究院, 2006.
|
[37]
|
胡泽华, 王佳, 孙伟力, 等. 基准模型keff对核数据的灵敏度分析及不确定度量化[J]. 原子能科学技术, 2013, 47(增刊): 312.
|
[38]
|
刘勇, 曹良志, 吴宏春, 等. 基于经典微扰理论的特征值灵敏度和不确定度分析[J]. 原子能科学技术, 2015, 49(7): 1247.
|
[39]
|
丘意书, 梁金刚, 余健开, 等. RMC程序敏感性分析功能的并行策略与验证[J]. 核动力工程, 2015, 36(3): 152-156.
|
[40]
|
Rhodes, J., Smith, K. and Lee, D. (2006) CASMO-5 Development and Applications. Proceedings of the PHYSOR-2006 Conference, ANS Topical Meeting on Reactor Physics, Vancouver, 10-14 September 2006, 144.
|
[41]
|
康慧伦. 压水堆物理-热工多尺度耦合计算研究[D]: [硕士学位论文]. 哈尔滨: 哈尔滨工程大学, 2018.
|
[42]
|
Ánchel, F., Barrachina, T., Miró, R., et al. (2012) Uncertainty and Sensitivity Analysis in the Neutronic Parameters Generation for BWR and PWR Coupled Thermal-Hydraulic-Neutronic Simulations. Nuclear Engineering and Design, 246, 98-106. https://doi.org/10.1016/j.nucengdes.2011.11.016
|
[43]
|
Gajev, I., Ma, W. and Kozlowski, T. (2014) Sensitivity Analysis of Input Uncertain Parameters on BWR Stability Using TRACE/PARCS. Annals of Nuclear Energy, 67, 49-58. https://doi.org/10.1016/j.anucene.2013.10.016
|
[44]
|
Mesado, C., Garcia-Fenoll, M., Miró, R., et al. (2015) Control Rod Drop Transient: Uncertainty and Sensitivity Analysis of Thermal-Hydraulic Variables Using a 3D Model with TRACE V5.0P3/PARCS 3.0. 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-16), Chicago, 30 August-4 September 2015, 611-626.
|
[45]
|
Pericas, R., Ivanov, K., Reventós, F., et al. (2017) Comparison of Best-Estimate plus Uncertainty and Conservative Methodologies for a PWR MSLB Analysis Using a Coupled 3-D Neu-tron-Kinetics/Thermal-Hydraulic Code. Nuclear Technology, 198, 193-201. https://doi.org/10.1080/00295450.2017.1299493
|
[46]
|
Miglierini, B., Kozlowski, T. and Kopecek, V. (2019) Un-certainty Analysis of Rod Ejection Accident in VVER-1000 Reactor. Annals of Nuclear Energy, 132, 628-635. https://doi.org/10.1016/j.anucene.2019.06.061
|
[47]
|
Zeng, K., Hou, J., Ivanov, K., et al. (2019) Uncertainty Quanti-fication and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core. Nuclear Technology, 205, 1618-1637.
https://doi.org/10.1080/00295450.2019.1580533
|
[48]
|
Salah, A.B., Kliem, S., Rohde, U., et al. (2006) Uncertainty and Sensitivity Analyses of the Kozloduy Pump Trip Test Using Coupled Thermal-Hydraulic 3D Kinetics Code. Nuclear Engineering and Design, 236, 1240-1255.
https://doi.org/10.1016/j.nucengdes.2005.11.005
|
[49]
|
Mesado, C., Soler, A., Barrachina, T., et al. (2012) Uncer-tainty and Sensitivity of Neutron Kinetic Parameters in the Dynamic Response of a PWR Rod Ejection Accident Coupled Simulation. Science and Technology of Nuclear Installations, 2012, Article ID: 625878. https://doi.org/10.1155/2012/625878
|
[50]
|
Grgic, D., Cavlina, N., Petruzzi, A., et al. (2013) Coupled Code Analysis of the Rod Withdrawal at Power Accident including Uncertainty Evaluation Using CIAU-TN Method.
|
[51]
|
Pan, X., Jia, B., Han, J., et al. (2017) Systematic and Quantitative Uncertainty Analysis for Rod Ejection Accident of Pressurized Wa-ter Reactor. Energy Procedia, 127, 369-376. https://doi.org/10.1016/j.egypro.2017.08.086
|
[52]
|
Avvakumov, A., Malofeev, V. and Sidorov, V. (2007) Spatial Effects and Uncertainty Analysis for Rod Ejection Accidents in a PWR. Of-fice of Nuclear Regulatory Research, US Nuclear Regulatory Commission.
|
[53]
|
Panka, I. (2004) Uncertainty Analysis for Control Rod Ejection Accidents Simulated by KIKO3D/TRABCO Code System.
|
[54]
|
Pasichnyk, I., Nikonov, S., Zwermann, W., et al. (2016) Coupled Code Analysis of Uncertainty and Sensitivity of Kalinin-3 Benchmark. Kerntechnik, 81, 427-431. https://doi.org/10.3139/124.110713
|
[55]
|
Perin, Y. and Escalante, J.J. (2017) Application of the Best-Estimate plus Uncertainty Approach on a BWR ATWS Transient Using the NURESIM European Code Platform. Nuclear Engineering and Design, 321, 48-56.
https://doi.org/10.1016/j.nucengdes.2017.05.018
|
[56]
|
Le Pallec, J.C., Studer, E. and Royer, E. (2003) PWR Rod Ejection Accident: Uncertainty Analysis on a High Burn-Up Core Configuration.
|
[57]
|
Delipei, G., Garnier, J., Le Pallec, J.C., et al. (2018) Multi-Physics Uncertainties Propagation in a PWR Rod Ejection Accident Modeling-Analysis Meth-odology and First Results. ANS Best Estimate plus Uncertainty International Conference (BEPU 2018), Lucca, 13-18 May 2018.
|
[58]
|
Delipei, G.K., Garnier, J., Le Pallec, J.C., et al. (2019) Uncertainty Analysis Methodology for Mul-ti-Physics Coupled Rod Ejection Accident. International Conference on Mathematics and Computational Methods Ap-plied to Nuclear Science and Engineering (M&C 2019), Portland, 25-29 August 2019.
|
[59]
|
Sargeni, A. and Ivanov, E. (2021) An IRSN Contribution to the UAM Project: Thermal-Hydraulic and Neutronic Uncertainties Propagation in a Rod Ejection, First Results. EPJ Web of Conferences. EDP Sciences, 247, Article ID: 07003. https://doi.org/10.1051/epjconf/202124707003
|
[60]
|
杨文, 田兆斐, 陈广亮. 基于确定性采样的不确定性分析[J]. 核动力工程, 2020, 41(S1): 42-45.
|
[61]
|
郭家丰. 压水堆燃料棒束物理-热工耦合计算与不确定性分析[D]: [硕士学位论文]. 哈尔滨: 哈尔滨工程大学, 2020.
|
[62]
|
雷洲阳. 基于CFD物理热工耦合的池式快堆UTOP事故不确定性分析研究[D]: [硕士学位论文]. 衡阳: 南华大学, 2021.
|
[63]
|
Delipei, G.K., Rouxelin, P., Abarca, A., et al. (2022) CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification. Energies, 15, Article No. 5226.
https://doi.org/10.3390/en15145226
|
[64]
|
Popova, E.D. and Elishakoff, I. (2020) Novel Interval Model Applied to Derived Variables in Static and Structural Problems. Archive of Applied Mechanics, 90, 869-881. https://doi.org/10.1007/s00419-019-01644-8
|
[65]
|
Naskar, S., Mukhopadhyay, T. and Sriramula, S. (2019) Spa-tially Varying Fuzzy Multi-Scale Uncertainty Propagation in Unidirectional Fibre Reinforced Composites. Composite Structures, 209, 940-967.
https://doi.org/10.1016/j.compstruct.2018.09.090
|
[66]
|
Shafer, G. (2016) A Mathematical Theory of Evidence Turns 40. International Journal of Approximate Reasoning, 79, 7-25. https://doi.org/10.1016/j.ijar.2016.07.009
|
[67]
|
Liu, H.B., Jiang, C., Jia, X.Y., et al. (2018) A New Uncertainty Propagation Method for Problems with Parameterized Proba-bility-Boxes. Reliability Engineering & System Safety, 172, 64-73. https://doi.org/10.1016/j.ress.2017.12.004
|
[68]
|
张保强, 苏国强, 展铭, 等. 概率盒框架下多响应模型确认度量方法[J]. 控制与决策, 2019, 34(12): 2642-2648.
|