集成缓冲材料对锶的长期阻滞效应

缓冲材料作为高放废物处置库中多重屏障体系的最后一道人工屏障,其对放射性核素的阻滞性能将直接影响到处置库的长期稳定性和安全性。以具有低渗透性和良好的膨胀自愈性的膨润土作为集成缓冲材料的基材,以沸石和黄铁矿作为矿物添加剂,三者按照质量比为63∶27∶10均匀混合构成集成缓冲材料B7ZP,并采用恒定源扩散实验分析了锶在干密度为1.70g/cm3试样中的扩散特性,结果表明,B7ZP缓冲材料对锶具有良好的阻滞性能,其表观扩散系数为3.30×10（-12） m2/s。同时,以多孔介质污染物迁移理论为依据,建立了锶在集成缓冲材料B7ZP中迁移的对流-弥散-吸附多场耦合方程,并应用Matlab软件分析了不同的...

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Bibliographic Details
Published in核化学与放射化学 Vol. 39; no. 3; pp. 235 - 242
Main Author 王哲 易发成
Format Journal Article
LanguageChinese
Published 西南科技大学核废物与环境安全国防重点学科实验室,四川绵阳621010 2017
中国科学技术大学地球与空间科学学院,安徽合肥230026%西南科技大学核废物与环境安全国防重点学科实验室,四川绵阳,621010
Subjects
锶
阻滞效应
集成缓冲材料
高放废物地质处置
集成缓冲材料
integrated buffer material
锶
retardative effect
strontium
阻滞效应
高放废物地质处置
geological disposal of high level radioactive waste
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ISSN0253-9950
DOI10.7538/hhx.2017.39.03.0235

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Summary:缓冲材料作为高放废物处置库中多重屏障体系的最后一道人工屏障,其对放射性核素的阻滞性能将直接影响到处置库的长期稳定性和安全性。以具有低渗透性和良好的膨胀自愈性的膨润土作为集成缓冲材料的基材,以沸石和黄铁矿作为矿物添加剂,三者按照质量比为63∶27∶10均匀混合构成集成缓冲材料B7ZP,并采用恒定源扩散实验分析了锶在干密度为1.70g/cm3试样中的扩散特性,结果表明,B7ZP缓冲材料对锶具有良好的阻滞性能,其表观扩散系数为3.30×10（-12） m2/s。同时,以多孔介质污染物迁移理论为依据,建立了锶在集成缓冲材料B7ZP中迁移的对流-弥散-吸附多场耦合方程,并应用Matlab软件分析了不同的时间尺度、渗流速率、表观扩散系数和阻滞因子等因素下集成缓冲材料B7ZP对锶的长期阻滞性能,为高放废物处置库的缓冲材料设计和长期阻滞性能评价提供科学依据。
Bibliography:11-2045/TL
Buffer material was the last artificial barrier of high-level radioactive waste repository, and its retardation capability to radioactive nuclides would directly affect the security and stability of the repository system. Bentonite was a suitable mineral, which can be used to build an integrated buffer material because of low hydraulic conductivity, good swelling and sealing properties, plasticity and high sorption capacity. Bentonite-zeolite-pyrite type integrated buffer material was constituted by the bentonite-zeolite-pyrite weight ratio was 63 ： 27 ： 10 （abbreviated as BTZP）, that zeolite and pyrite were chosen as mineral additires. Then constant source diffusion experiment was carried out to investigate strontium diffusibility in B7ZP with initial dry density of 1.70 g/cm3. The experimental results indicate that B7ZP has good retardation capability for strontium, and the apparent diffusion coefficient of strontium is 3.3× 10 ^-12 m2/s, smaller in B7ZP than in pure bentonite. The convec tion-dif
ISSN:0253-9950
DOI:10.7538/hhx.2017.39.03.0235