高放废物处置巷道尺度岩体适宜性评价

doi:10.11720/wtyht.2024.1553

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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Q_HLW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Q_HLW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。

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	叶勇
	陈亮
	刘健

关键词 ：高放废物地质处置, 岩体适宜性评价, 处置巷道尺度

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 (Q_HLW) 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 Q_HLW 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.

Key words： geological disposal of high-level radioactive waste evaluation of rock mass suitability tunnel-scale

收稿日期: 2023-12-21 修回日期: 2024-07-29 出版日期: 2024-12-20

ZTFLH:	P587
	P597.3

基金资助:国防科工局核设施退役与放射性废物治理专项(科工二司[2020]基础科研计划(JCKY2020201C003))

通讯作者: 陈亮(1982-),男,山东东营人,正高级工程师,博士,长期从事高放废物地质处置技术研究工作。Email:chenliang@briug.cn

引用本文:

叶勇, 陈亮, 刘健. 高放废物处置巷道尺度岩体适宜性评价[J]. 物探与化探, 2024, 48(6): 1545-1552.
YE Yong, CHEN Liang, LIU Jian. Tunnel-scale evaluation of rock mass suitability for the disposal of high-level radioactive waste. Geophysical and Geochemical Exploration, 2024, 48(6): 1545-1552.

链接本文:

https://www.wutanyuhuatan.com/CN/10.11720/wtyht.2024.1553 或 https://www.wutanyuhuatan.com/CN/Y2024/V48/I6/1545

处置罐体材料	地下水化学环境	$C c h m, c T$
铜	同时满足以下2个条件:(1)7<pH<10;(2)[SO₄^2-]<[Cl^-]<2 500 mg·L^-1	1.0
	仅满足以下1个条件:(1)7<pH<10;(2)[SO₄^2-]<[Cl^-]<2 500 mg·L^-1	0.8
	以下2个条件均不满足:(1)7<pH<10;(2)[SO₄^2-]<[Cl^-]<2 500 mg·L^-1	0.1
碳钢	同时满足以下2个条件:(1)8<pH<9.5;(2)[HCO₃^-]<6 000 mg·L^-1且[Cl^-]<3 000 mg·L^-1	1.0
	仅满足以下1个条件:(1)8<pH<9.5;(2)[HCO₃^-]<6 000 mg·L^-1且[Cl^-]<3 000 mg·L^-1	0.8
	以下2个条件均不满足:(1)8<pH<9.5;(2)[HCO₃^-]<6 000 mg·L^-1且[Cl^-]<3 000 mg·L^-1	0.1

Table 1 处置罐体抗腐蚀系数

C c h m, c T

取值范围^[6]

地下化学环境	$C c h m, b T$ 取值
同时满足以下3个条件:(1)6<pH<10;(2)TDS<10 g·L^-1;3)I>10^-3mol·L^-1	1.0
满足以下3个条件中的2个:(1)6<pH<10;(2)TDS<10 g·L^-1;3)I>10^-3mol·L^-1	0.8
仅能满足以下3个条件中的1个或均不满足:(1)6<pH<10;(2)TDS<10 g·L^-1;3)I>10^-3mol·L^-1	0.1

Table 2 缓冲材料抗腐蚀

C c h m, b T

取值范围^[6]

$Q H L W T$	质量等级		适宜性描述
(400,+∞]	Ⅰ	适宜	岩体适宜性程度高,适合作为处置岩体
(10,400]	Ⅱ	基本适宜	岩体适宜性程度一般,需要做更深入的研究,确定是否存在其他影响适宜性因素
≤10	Ⅲ	不适宜	对该岩体应采取避开策略

Table 3 Q_HLW法处置巷道尺度围岩适宜性评价标准

Fig.1 ONKALO场址示范处置区域布局示意

Fig.2 示范巷道DT1断裂带及裂隙分布^[12]

Fig.3 示范巷道DT1裂隙影响指标取值

Table 4 示范巷道DT1地下水化学特征^[13]

Fig.4 示范巷道DT1岩体渗透特性测量值^[14]

Fig.5 示范巷道DT1渗透特性取值

Fig.6 示范巷道DT1流量分布^[14]

Fig.7 示范巷道DT1渗透特性取值

Fig.8 示范巷道DT1岩体完整指标Q'值^[14]

Fig.9 示范巷道DT1 Q_HLW适宜性评价结果

Fig.10 示范巷道DT1 Q_HLW适宜性评价结果

Fig.11 示范巷道DT1 RSC适宜性评价结果^[2]

Fig.12 Q_HLW工程评价系统示意

Fig.13 示范巷道DT1处置坑布置示意^[18]

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