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

doi:10.13722/j.cnki.jrme.2017.1044

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摘要传统岩体工程质量评价方法仅考虑了地下工程的可建造性要求，未考虑放射性废物处置工程对岩体长期安全性需求，在高放废物处置领域的应用具有明显局限性。基于国际上广泛应用的Q岩体工程质量分级法，通过引入影响处置工程长期安全的围岩特性因子，首次建立定量的高放废物处置岩体适宜性评价方法体系QHLW。其中，岩体断裂带分布、地下水化学特性、温度影响、岩体渗透性能等特性对处置工程长期安全性影响得到了系统的考虑。与传统方法相比，QHLW方法能够系统反应处置库工程长期稳定性和安全性需求，可为处置库候选场址适宜性评价和工程优化布置提供有效的理论支撑。采用该方法，基于场址特性评价基础数据，对从我国甘肃北山、新疆、内蒙古三大预选区筛选出的9个地下实验室候选场址适宜性进行综合评价研究，确定各候选场址的适宜性指标。评价结果表明，新场、沙枣园、算井子、雅满苏及诺日公候选场址均可认为是高放废物处置地下实验室适宜场址，以北山预选区新场场址适宜性最高。

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关键词 ：岩石力学, 高放废物处置, 岩体适宜性评价, 地下实验室选址, 新场场址

Abstract：In this paper，a new system of rock suitability classification named QHLW is introduced to evaluate the suitability of the host rock for high-level radioactive waste(HLW) disposal at different scales. The system is developed on the basis of Q-system，and considers both the long-term safety and constructability requirements of the host rock for disposal. Some additional parameters，including the fracture zone distribution，groundwater chemistry and thermal effect are also taken into account in light of their significant influence on the long-term safety of HLW disposal. In the QHLW system，the suitability of host rock is classified into three classes at the repository and tunnel scales. The suitability of nine potential sites of underground research laboratory(URL) for HLW disposal located in Beishan，Xinjiang and Inner Mongolia regions are evaluated with this classification system. The Xinchang site in Beishan region is classified as the most suitable URL site according to the results of analysis.

Key words： rock mechanics high-level radioactive waste disposal rock suitability classification site selection of underground research laboratory Xinchang site

引用本文:

陈亮，王驹，刘健，刘亦亨. 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 Liang，WANG Ju，LIU Jian，LIU Yiheng. 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. , 2018, 37(6): 1385-1394.

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http://www.rockmech.org/CN/10.13722/j.cnki.jrme.2017.1044 或 http://www.rockmech.org/CN/Y2018/V37/I6/1385

[3]	Nuclear Energy Agency. Methods for safety assessment of geological disposal facilities for radioactive waste[R]. [S. l.]：Radioactive Waste Management，2012.
[13]	MCEWEN T，ARO S，KOSUNEN P，et al. Rock suitability classification RSC 2012[R]. Olkiluo：Posiva Oy，2012.
[8]	AIKAS K，RIEKKOLA R. Locating of the high level waste repository[R]. Helsinki：Nuclear Waste Commission of Finnish Power Companies，2000.
[6]	BIENIAWSKI Z T. Engineering rock mass classifications[M]. New York：Wiley，1989：51-72.
[16]	MUNIER R，HOKMARK H. Respect distances—rationale and means of computation[R]. Stockholm：Swedish Nuclear Fuel and Waste Management Co(SKB)，2004.
[26]	Swedish Nuclear Fuel and Waste Management Co.. SR 97-Processes in the repository evolution[R]. Stockholm：Swedish Nuclear Fuel and Waste Management Co(SKB)，1999.
[27]	NAGRA K I. Safety assessment report[R]. Wettingen：Nagra，1994.
[10]	SINGH B，GOEL R K. Rock mass classification-A practical approach in civil engineering[M]. Amsterdam/New York/Oxford：Elsevier，1999：17-117.
[12]	HAGROS A. Host rock classification(HRC) System for nuclear waste disposal in crystalline bedrock[R]. Helsinki：University of Helsinki，2006.
[22]	HAGROS A，AIKAS K，MCEWEN T，et al. Host rock classification- phase 2：influence of host rock properties[R]. Olkiluoto：Posiva Oy，2003.
[1]	潘自强，钱七虎. 高放废物地质处置战略研究[M]. 北京：原子能出版社，2009：15-17.(PAN Ziqiang，QIAN Qihu. Strategy research on high-level radioactive waste geological disposal[M]. Beijing：Publishing House of Atomic Energy，2009：15-17.(in Chinese))
[7]	中华人民共和国国家标准编写组. GB/T 50218—2014工程岩体分级标准[S]. 北京：中国计划出版社，2014.(The National Standards Compilation Group of People?s Republic of China. GB/T 50218—2014 Standard for engineering classification of rock masses[S]. Beijing：China Planning Press，2014.(in Chinese))
[11]	MAKURAT A，LOSET F. Results of Q-and RMR logging and tilt testing of cores from bore holes KA2511A，KAS02 and KA2598A at Aspo HRL[R]. Stockholm：Swedish Nuclear Fuel and Waste Management Co(SKB)，2001.
[17]	BONILLA M G，MARK R K，LIENKAEMPER J J. Statistical relations among earthquake magnitude，surface rupture length，and surface fault displacement[J]. Bulletin of the Seismological Society of America，1984，74(6)：2 379-2 411.
[21]	Swedish Nuclear Fuel and Waste Management Co.. Interim main report of the safety assessment SR-Can[R]. Stockholm：Swedish Nuclear Fuel and Waste Management Co(SKB)，2004.
[23]	HEUZE F E. High-temperature mechanical，physical and thermal properties of granitic rocks，a review[J]. International Journal of Rock Mechanics and Mining Sciences and Geomechanics Abstracts，1983，20(1)：3-10.
[31]	赵宏刚. 高放废物处置库热传导特性及处置硐室稳定性研究——以甘肃北山预选区为例[博士学位论文][D]. 北京：核工业北京地质研究院，2009.(ZHAO Honggang. A study of thermal conductivity property and tunnel stability of high level radioactive waste repository—the case of Beishan preselected site，Gansu province[Ph. D. Thesis][D]. Beijing：Beijing Research Institute of Uranium Geology，2009.(in Chinese)).
[2]	IAEA. Scientific and technical basis for the geological disposal of radioactive wastes[R]. IAEA Technical Rapport-413，Vienna：International Atomic Energy Agency，2003.
[4]	WANG J. High-level radioactive waste disposal in China：update 2010[J]. Journal of Rock Mechanics and Geotechnical Engineering，2010，2(1)：1-11.
[9]	ROSHOFF K，LANARO F，JING L. Strategy for a rock mechanics site descriptive model：development and testing of the empirical approach[R]. Stockholm：Swedish Nuclear Fuel and Waste Management Co(SKB)，2002.
[14]	CHEN L，WANG J，ZONG Z H，et al. A new rock mass classification system QHLW for high-level radioactive waste disposal[J]. Engineering Geology，2015，190(2)：33-51.
[18]	WELLS D L，COPPERSMITH K J. New empirical relationships among magnitude，rupture length，rupture width，rupture area，and surface displacement[J]. Bulletin of the Seismological Society of America，1994，84(4)：974-1 002
[19]	KIM Y S，SANDERSON D J. The relationship between displacement and length of faults：a review[J]. Earth-Science Reviews，2005，68：317-334.
[5]	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.
[15]	中国国防科学技术工业委员会，中国国家环境保护总局. 高放废物地质处置研究开发规划指南[M]. [S. l.]：[s. n.]，2006：1-41.(China National Committee of Defense Science and Technology Industry and China National Administration of Environmental Protection. Guidelines for research and development of geological disposal of high level radioactive waste[M]. [S. l.]：[s. n.]，2006：1-41.(in Chinese))
[25]	MARTIN C D，CHANDLER N A. The progressive fracture of Lac du Bonnet granite[J]. International Journal of Rock Mechanics and Mining Sciences and Geomechanics Abstracts，1994，31(6)：643-659.
[29]	王驹，宗自华，金远新，等. 高放废物处置库预选区综合比选——主观定量评价方法[C]// 第四届废物地下处置学术研讨会论文集. [S. l.]：[s. n.]，2012：3-10.(WANG Ju，ZONG Zihua，JIN Yuxin，et al. Comprehensive comparison of preselected regions for a high level radioactive waste repository：a subjective quantitative evaluation method[C]// Proceedings of the 4th Conference of Waste Disposal. [S. l.]：[s. n.]，2012：3-10.(in Chinese))
[35]	王春萍，陈亮，梁家玮，等. 考虑温度影响的花岗岩蠕变全过程本构模型研究[J]. 岩土力学，2014，35(9)：2 493-2 500.(WANG Chunping，CHEN Liang，LIANG Jiawei，et al. Creep constitutive model for full creep process of granite considering thermal effect[J]. Rock and Soil Mechanics，2014，35(9)：2 493-2 500.(in Chinese))
[20]	ANDERSSON J，STROM A，SVEMAR C，et al. What requirements does the KBS-3 repository make on the host rock? Geoscientific suitability indicators and criteria for siting and site evaluation[R]. Stockholm：Swedish Nuclear Fuel and Waste Management Co(SKB)，2000.
[24]	LIN Q X，LIU Y M，THAM L G，et al. Time-dependent strength degradation of granite[J]. International Journal of Rock Mechanics and Mining Sciences，1983，46(1)：1 103-1 114.
[28]	GRIMSTAD E，BARTON N. Updating of the Q-system for NMT[C]// International Symposium on Spayed Concrete—Modern Use of Wet Mix Sprayed Concrete for Underground Support. Fagernes：[s. n.]，1993.
[32]	王驹，苏锐，陈亮，等. 中国高放废物处置地下实验室选址报告[R]. 北京：核工业北京地质研究院，2016.(WANG Ju，SU Rui，CHEN Liang，et al. Site selection of the underground research laboratory for geological disposal in China[R]. Beijing：Beijing Research Institute of Uranium Geology，2016.(in Chinese))
[34]	刘月妙，王驹，谭国焕，等. 高放废物处置北山预选区深部完整岩石基本物理力学性能及时温效应[J]. 岩石力学与工程学报，2007，26(10)：2 034-2 042.(LIU Yuemiao，WANG Ju，TAN Guohuan，et al. Basic physico-mechanical properties and time-temperature effect of deep intact rock from Beishan pre-selected area for high-level radioactive waste disposal[J]. Chinese Journal of Rock Mechanics and Engineering，2007，26(10)：2 034-2 042.(in Chinese))
[30]	王驹，苏锐，陈亮，等. 甘肃北山高放废物地质处置地下实验室若干战略问题的考虑[J]. 世界核地质科学，2014，31(增1)：125-130.(WANG Ju，SU Rui，CHEN Liang，et al. Considierations on several strategic problems on underground research laboratory for high-level radioactive waste disposal in Beishan，Gansu province[J]. World Nuclear Geoscience，2014，31(Supp.1)：125-130.(in Chinese))
[33]	JARI L. Safety case for the disposal of spent nuclear fuel at Olkiluoto definition of reference and bounding groundwaters，buffer and backfill porewaters[R]. [S. l.]：POSIVA，2014.