Tunnel-scale evaluation of rock mass suitability for the disposal of high-level radioactive waste
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摘要: 岩体适宜性评价是高放废物处置库选址和设计的核心内容之一, 以判断场址岩体是否满足处置库长期包容和隔离核素的功能要求。在已提出的场址尺度QHLW岩体适宜性评价方法的基础上, 本文进一步发展了处置巷道尺度岩体适宜评价准则, 建立了“预评价+最终评价”两阶段的评价体系。同时, 结合芬兰高放废物处置ONKALO地下实验室场址示范巷道1(DT1)揭露的地质水文信息, 对处置巷道尺度两个阶段的评级标准体系进行测试和验证。对比分析优化QHLW获得的适宜性评价结果与芬兰RSC岩体适宜性评价方法定性评价结果, 发现两种方法得出的评价结果基本一致, 验证了处置巷道尺度岩体适宜性评价方法的可行性。Abstract: Rock mass suitability evaluation is a core part of the siting and design of a disposal repository for high-level radioactive waste, aiming to determine whether the rock masses at the site meet the functional requirements for long-term containment and radionuclides isolation. Based on the previously proposed site-scale evaluation method (QHLW) of rock mass suitability, this study further developed criteria for the tunnel-scale evaluation of rock mass suitability and established a two-phase evaluation system consisting of pre-evaluation and final evaluation. Additionally, in combination with geological and hydrological data revealed by demonstration tunnel 1 (DT1) at the site of the ONKALO underground research laboratory in Finland, this study tested and verified the criteria of the two-phase evaluation system on the disposal tunnel scale. The comparison between the suitability evaluation results obtained using the optimized QHLW and the qualitative evaluation results determined using the rock suitability classification (RSC) rock mass grading method indicates that both methods yielded roughly consistent results. This confirms the feasibility of the tunnel-scale evaluation method of rock mass suitability.
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[1] IEAE.Scientific and technical basis for the geological disposal of radioactive wastes[R].Vienna:International Atomic Energy Agency, 2003.
[2] Mcewen T, Mattila J, Askokä P.Rock suitability classification-RSC[R].Olkiluoto:Posiva Oy, 2012.
[3] Chen L, Wang J, Liu J.A new rock mass classication system QHLW for high-level radioactive waste disposal[J].Engineering Geology, 2015, 190:33-51.
[4] 陈亮, 王驹, 刘健, 等.高放废物地质处置岩体适宜性评价方法(QHLW)及其在地下实验室选址中的应用研究[J].岩石力学与工程学报, 2018, 37(6):1385-1394.
Chen L, Wang J, Liu J, et al.A new system of rock suitability classification QHLW for high-level radioactive waste disposal and its application in the selection of URL site in China[J].Chinese Journal of Rock Mechanics and Engineering, 2018, 37(6):1385-1394.
[5] Heta L.Terminology report respect distance:The use of the term respect distance in Posiva and SKB[R].Olkiluoto:Posiva Oy, 2007.
[6] 刘亦亨.高放废物处置库巷道尺度岩体适宜性评价方法(Q_(HLW))研究[D].北京:核工业北京地质研究院, 2019.Liu Y H.Study on the evaluation method of roadway-scale rock mass suitability (Q_(HLW)) for high level radioactive waste repository[D].Beijing:Beijing Research Institute of Uranium Geology, 2019.
[7] Kierar I.Safety assessment report[R].Wettingen:Nagra, 1994.
[8] Munier R, Hokmark H.Respect distances-rationale and means of computation[R].Stockholm:Swedish Nuclear Fuel and Waste Management Co(SKB), 2004.
[9] ikäs S B, Pete A.Exploring conditioned simulations of discrete fracture networks in support of hydraulic acceptance of deposition holes[R].Olkiluoto:Posiva Oy, 2018.
[10] Barton N, Lien R, Lunde J.Engineering classification of rock masses for the design of tunnel support[J].Rock Mechanics, 1974, 6(4):189-236.
[11] Anna R, Ilkka L S M, Paula K.Design and construction of equipmentand experimental deposition holes in ONKALO demonstration tunnel 1[R].Olkiluoto:Posiva Oy, 2017.
[12] Salminen P.Geometrical and mechanical properties of the fractures and brittle deformation zones based on the ONKALO tunnel mapping the shafts and the demonstration tunnels[R].Olkiluoto:Posiva Oy, 2015.
[13] Nina P, Eliisa H, Ylä-Mella M.Groundwater sampling at Olkiluoto, Eurajoki from the borehole OL-KR6 during a long-term pumping test in 2004[R].Olkiluoto:Posiva Oy, 2006.
[14] Komulainen J, Pekkanen J.Difference flow measurements and hydraulic interference test in ONKALO at Olkiluoto drill holes ONK-PH16 and ONK-PH17[R].Eurajoki:Posiva Oy, 2012.
[15] Hakala M.In situ stress measurements in ONKALO with LVDT-Cell[R].Olkiluoto:Posiva Oy, 2017.
[16] Kärnbränslehantering S.Detailed site investigation programme for the construction and operation of the repository for spent nuclear fuel[R].Olkiluoto:Posiva Oy, 2018.
[17] Krnbrnslehantering S.The integrated sulfide project-Summary Report[R].Olkiluoto:Posiva Oy, 2019.
[18] Markström I, SKA.Rock visualization system[R].Olkiluoto:Posiva Oy, 2015.
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