收稿日期: 2022-12-17
修回日期: 2023-04-06
网络出版日期: 2023-09-20
基金资助
国家自然科学基金项目“压缩空气储能地下储气库FRP密封结构界面失效机理与设计方法研究”(52178381)
Preliminary Study on Static and Dynamic Stability of Canister for High-level Radioactive Nuclear Waste Disposal Based on Discrete Element Method
Received date: 2022-12-17
Revised date: 2023-04-06
Online published: 2023-09-20
核废料储罐是核废料处理工程屏障的核心部分,其静动力学稳定性至关重要。基于碳化硅材料的核废料储罐,考虑深部岩石—储罐的相互作用特点,采用试验与模拟相结合的方法开展研究。首先对碳化硅的抗拉强度特征进行了研究,分析了深埋条件下的储罐受力特点和规律;其次,研究了自由落体与岩石撞击条件下储罐的动态受力规律和基本破坏形式,并考虑岩石破碎所带来的影响。结果显示:碳化硅是相对脆性材料,其抗拉强度存在一定变化区间;在深埋条件下,埋深、水平与竖向地应力比对储罐受力有较大的影响;运输时自由跌落的高度和倾角对储罐局部集中拉应力有较大的影响;岩石撞击时储罐内的拉应力受岩石质量和撞击发生时岩石—储罐接触类型的控制,考虑岩石撞击破碎会大幅削弱撞击附加应力,岩块间黏聚力和内摩擦角越大,岩石撞击力也越大,岩块间抗拉强度对撞击力的影响相对较小。虽然在自由跌落与岩石撞击的工况下会发生局部破坏,但通过外附一定厚度缓冲层并合理安置,可保证储罐的静动力稳定性。
赵亚楠 , 赵一航 , 蒋中明 , 赵红敏 . 基于离散元法的高放核废料储罐静动力稳定性初步研究[J]. 黄金科学技术, 2023 , 31(4) : 592 -604 . DOI: 10.11872/j.issn.1005-2518.2023.04.010
Canister for high-level radioactive waste is a core part in nuclear waste disposal barrier,and its static and dynamic stability during transportation,installation,and deep buried operation is of great importance.A silicon carbide(SiC) material based canister was proposed in this paper.The material has remarkable chemical stability,but its brittleness may be the key to restrict it application.In oder to investigate the static and dynamic stability of this canister,series of numerical simulations were performed using discrete element method,considering the physical nature of rock blocks and characteristics of interactions between rock and canister.The tensile strength characteristics of SiC was first investigated via specially designed lab and numerical tests.Comparison with analytical results has proved the reliability of adopted numerical method.The influence of disposal depth and horizontal to vertical stress ratio was then investigated.The dynamic loading behaviour pattern and basic failure mode of canister under free fall and rock impact were investigated,and the influence of rock fragmentation was mainly considered.The results show that the silicon carbide material is relatively brittle,with tested tensile strength between 150 MPa and 200 MPa,compared to its very high compressive strength.The tensile strength of silicon carbide was chosen 150 MPa for safety reason in later analysis.However,this value of 150 MPa is higher than the tensile or even compressive strength of ordinary rocks.The canister can survive under 1 200 m depth,horizontal to vertical stress ratio of 3 with several disposal inclination angles.Under free fall,the maximum tensile stress in canister is determined by falling height and inclination angle.Upon rock fall without rock splitting,the maximum tensile stress in canister is determined by rock weight and contact type between rock and canister.Inclusion of rock splitting in model calculation can produce stress much lower than by traditional continuum method.The tip of the rock will crack first once the rock is hitting the canister,leaving the canister safe in the first place,which is different from that in continuum analysis.This implies the energy dissipation between rock blocks due to fracturing of rock during rock impact is not negligible.As the cohesion and residual friction angle between rock blocks increase,the stress induced in canister also increases,while the tension makes limited contribution to elevated stress.Another interesting finding is that as the rock block volume ratio gets smaller,the stress induced by impacting rock decreases first but then keeps to a constant value once certain threshold is reached.This suggests by reaching certain rock block volume ratio may be enough to reproduce dynamic impact-induced cracking,instead of decreasing rock block size constantly.Although local failure is expected under dynamic impact,a soft buffer layer with certain thickness outside the canister can guarantee static and dynamic stability of SiC canister together with appropriate emplacement.
null | Bj?rkbacka ?, Hosseinpour S, Johnson M,et al,2013.Radiation induced corrosion of copper for spent nuclear fuel storage[J].Radiation Physics and Chemistry,92:80-86. |
null | B?rgesson L, Chijimatsu M, Fujita T,et al,2001.Thermo-hydro-mechanical characterisation of a bentonite-based buffer material by laboratory tests and numerical back analyses[J].International Journal of Rock Mechanics and Mining Sciences,38(1):95-104. |
null | Ghazvinian E, Diederichs M S, Quey R,2014.3D random Voronoi grain-based models for simulation of brittle rock damage and fabric-guided micro-fracturing[J].Journal of Rock Mechanics and Geotechnical Engineering,6:506-521. |
null | Haslam J J, Farmer J C, Hopper R W,et al,2005.Ceramic coatings for a corrosion-resistant nuclear waste container evaluated in simulated ground water at 90 ℃[J].Metallurgical and Materials Transactions,A(36): 1085-1095. |
null | Hennig T, Stockmann M, Kühn M,2020.Simulation of diffusive uranium transport and sorption processes in the opalinus clay[J].Applied Geochemistry,123:104777. |
null | Hou Huiming, Hu Dawei, Zhou Hui,et al,2019.Thermo-hydro-mechanical coupling simulation method of surrounding rock in high-level radioactive waste repository considering effective meso-thermal parameters[J].Rock and Soil Mechanics,40(9):3625-3634. |
null | Itasca Consulting Group,2016.3DEC Manuals[M].Minneapolis:Itasca Consulting Group. |
null | Jiao Y Y, Fan S C, Zhao J,2005.Numerical investigation of joint effect on shock wave propagation in jointed rock masses[J].Journal of Testing and Evaluation,33(3):1-7. |
null | Lay L A,1983.Corrosion Resistance of Technical Ceramics[M].Teddington:Middlesex Her Majesty’s Stationery Office. |
null | Lee M S, Lee J Y, Choi H J,et al,2018.Evaluation of silicon carbide (SiC) for deep borehole disposal canister [J].Journal of the Nuclear Fuel Cycle and Waste Technology,16(2):233-242. |
null | Lee M Y, Brannon R M, Bronowski D R,2004.Uniaxial and triaxial compression tests of silicon carbide ceramics under quasi-static loading condition[R].Albuquerque:Sandia National Laboratory. |
null | McEachern D W, Wu W, Venneri F,2012.Performance of PyC,SiC and ZrC coatings in the geologic repository [J].Nuclear Engineering and Design,251:102-110. |
null | Metz V, Geckeis H, González-Robles E,et al,2012.Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel[J].Radiochimica Acta,100:699-713. |
null | Nasir O, Nguyen T S, Barnichon J D,et al,2017.Simulation of the hydromechanical behaviour of bentonite seals for the containment of radioactive wastes[J].Canadian Geotechnical Journal,54(8):1055-1070. |
null | Onofrei M, Raine D K, Brown L,et al,1984.Leaching studies of nonmetallic materials for nuclear fuel immobilization containers[C]//Proceedings of Materials Research Society Sy-mposium.Boston:Materials Research Society. |
null | Sellin P, Leupin O X,2013.The use of clay as an engineered barrier in radioactive-waste management—A review[J].Clays and Clay Minerals,61:477-498. |
null | Soroka I, Chae N, Jonsson M,2021.On the mechanism of γ-radiation-induced corrosion of copper in water[J].Corrosion Science,182:109279. |
null | Wang J,2010.High-level radioactive waste disposal in China: Update 2010[J].Journal of Rock Mechanics and Geotechnical Engineering,2:1-11. |
null | Wang Jianguo, Liang Shufeng, Gao Quanchen,et al,2018.Experimental study of jointed angles impact on energy transfer characteristics of simulated rock material[J].Journal of Central South University(Science and Technology),49(5):1237-1243. |
null | Xu Tao,2019.THM Coupling Process in Unsaturated Bentonite Buffer Material with Construction Joints and Self-Healing Effects[D].Beijing:Beijing Jiaotong University. |
null | Xu Xun,2021.Hydro-Thermal Evolution Law of Double-Layer Buffer in High-Level Radioactive Waste Repository[D].Yichang:China Three Gorges University. |
null | Zhao Yiwei, Wu Zhijun, Wang Xuhong,et al,2021.Numerical analysis of multi-field coupling of barrier system in deep geological repository for high-level radioactive waste[J].Journal of Central South University(Science and Technology),52(8):2557-2571. |
null | 侯会明,胡大伟,周辉,等,2019.考虑细观等效热学参数的高放废物处置库围岩应力—渗流—温度耦合模拟方法[J].岩土力学,40(9):3625-3634. |
null | 王建国,梁书锋,高全臣,等,2018.节理倾角对类岩石冲击能量传递影响的试验研究[J].中南大学学报(自然科学版),49(5):1237-1243. |
null | 许韬,2019.含施工接缝的非饱和膨润土缓冲材料热—水—力耦合过程及愈合效应[D].北京:北京交通大学. |
null | 许迅,2021.高放废物处置库双层缓冲层水—热演化规律[D].宜昌:三峡大学. |
null | 赵艺伟,吴志军,王旭宏,等,2021.高放废物深地质处置库屏障系统的多场耦合数值分析[J].中南大学学报(自然科学版),52(8):2557-2571. |
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