Ca^(2+)盐溶液在高庙子膨润土中的扩散研究北大核心CSCD

高放废物地质处置库近场地下水可能会对处置库内的屏障体系产生影响,降低处置库的安全稳定。为研究地下水中盐离子在处置库内缓冲回填体系的扩散规律,本文开展了静态无外荷载条件下内蒙古高庙子(GMZ)膨润土在Ca^(2+)盐溶液中自发渗吸的吸附扩散室内试验。从土的微观结构和经典扩散理论对Ca^(2+)在不同干密度和初始饱和度的膨润土试样中的自发扩散规律进行了分析。研究结果表明,在膨润土初始饱和度相同的情况下,试样阻滞系数随其干密度增加而增大,此时Ca^(2+)的扩散能力减弱;当膨润土干密度相同时,随着初始饱和度的增加基质吸力作用减弱,阻滞系数减小,Ca^(2+)的扩散能力减弱。     

多因素耦合作用下缓冲材料对铀的长期阻滞效应数值模拟北大核心CSCD

近场环境条件下核素在缓冲材料中的迁移扩散受控于温度场、渗流场、膨胀应力场和化学吸附场的耦合作用,其对核素的阻滞特性将影响到核素随地下水向处置库围岩迁移并返回生物圈的能力,开展多因素耦合作用下缓冲材料对铀的长期阻滞效应研究,对地质处置库的长期安全性评价具有重要的意义。本研究基于混合物理论、连续介质理论、质量守恒、动量守恒、能量守恒及溶质扩散的Fick定律,推导出饱和缓冲材料中核素迁移扩散的热-水-力-化耦合控制方程,并借助于COMSOL Multiphysics软件的直接全耦合求解优势,以自主研制的缓冲材料长期阻滞性能Mock-up实验装置为几何模型,采用内置接口和添加热-水-力-化耦合控制方程中的耦合项作为源项相结合方式,实现了多物理场耦合作用下铀在饱和缓冲材料中迁移扩散行为的直接耦合分析,其长期阻滞特性数值模拟结果表明:初期阶段铀在缓冲材料中迁移扩散较缓慢,迁移距离随时间增幅在1 m左右;中后期阶段,随缓冲材料对铀的吸附容量逐渐趋于饱和后,其迁移距离较初期阶段增加更为明显,迁移距离随时间增幅为3 m左右。多因素耦合下核素在饱和缓冲材料中迁移扩散的热-水-力-化耦合控制方程构建、求解及长期阻滞性能模拟研究的方法,能够为我国高放废物深地质处置库地下实验室开展1∶1工程尺度的工程屏障设计与安全性能评价提供技术参考。     

不同温度下Np（Ⅳ）在北山地下水中的溶解度

采用过饱和法研究了低氧条件下、30℃和60℃时Np(Ⅳ)在去离子水和甘肃北山地下水中的溶解度。结果表明,30℃时Np(Ⅳ)在去离子水和北山地下水中的溶解度分别为(3.4±1.0)×10-9mol/L和(1.0±0.3)×10-8mol/L;60℃时Np(Ⅳ)在去离子水和北山地下水中的溶解度分别为(1.9±0.6)×10-8mol/L和(3.7±0.5)×10-8mol/L;Np(Ⅳ)的溶解度随着温度升高而增加。同时利用SIT理论计算了实验条件下的热力学常数,确定了去离子水和北山地下水中的溶解度控制固相为Np(OH)4(am);去离子水体系中Np(Ⅳ)主要以Np(OH)4(aq)的形式存在,在北山地下水体系中Np(Ⅳ)主要以Np(OH)4(aq)和Np(CO3)2(OH)22-的形式存在。     

Sr^(2+) 在阳江花岗岩上的吸附行为北大核心CSCD

以阳江中低放核废物处置库围岩花岗岩为研究对象,通过静态吸附实验探究了阳江花岗岩围岩吸附Sr^(2+)的行为,详细研究了接触时间、初始浓度、反应温度、pH值、阴阳离子对花岗岩吸附行为的影响,并通过表征手段研究了阳江花岗岩的物化组成。结果表明:阳江花岗岩是一种主要由硅氧化物构成的岩石,吸附后其表面变得粗糙。吸附在5 d达到吸附平衡,属于化学吸附行为。吸附和Langmuir等温模型拟合效果更好,Sr^(2+)更多吸附在阳江花岗岩的表面。酸性和碱性环境均会削弱阳江花岗岩对Sr^(2+)的吸附能力,且升高温度和增大初始浓度均有利于吸附。地下水中存在的Ca^(2+)、Mg^(2+)、Fe^(3+)、NO_(3)^(-)均会抑制阳江花岗岩对Sr^(2+)的吸附,CO_(2)-3会和Sr^(2+)生成聚合物而干扰吸附。此研究可以为阳江中低放核废物处置库的安全评估提供一定参考。     

温度对^(75)Se(Ⅳ)在我国北山花岗岩中扩散影响的再思考北大核心CSCD

本文对Se在我国高放废物地质处置库预选围岩北山花岗岩中的扩散研究进行了总结,包括研究方法、获取的有关数据以及尚待开展的工作等,重点分析了温度对^(75)Se(Ⅳ)在北山花岗岩中扩散的影响及可能的影响机制,旨在为国内同行提供有益参考。     

衰变和吸附对放射性核素在花岗岩

为了获取关键核素在北山花岗岩中的有效扩散系数,依据125I-在甘肃北山深部花岗岩中的一维扩散曲线,用参数拟合方法得到了125I-在北山花岗岩中的有效扩散系数,并依据扩散方程讨论了衰变和吸附对扩散曲线的影响.研究结果表明,衰变常量和吸附速率常数对一维扩散曲线的影响各不相同,衰变常量的大小影响扩散曲线的形状,吸附速率常数的大小则影响扩散曲线的走势,不同核素的扩散曲线可有很大的差别.     

花岗岩介质中Sr、I和Pu的扩散行为

采用穿透扩散法研究了Sr、I和Pu等3种元素在花岗岩中的扩散行为,获得了26℃下离子强度为0.1mol/L的中性水溶液环境中Sr、I和Pu的有效扩散系数分别为(1.24±0.03)×10-13、(2.88±0.02)×10-13、(1.33±0.52)×10-13 m2/s。研究表明,水溶液与花岗岩平衡过程中核素的存在形态与化学种态的变化对其迁移行为有明显影响。     

Accelerated Leach Tests of SRL-165 High-Level Waste Glass in Deionized Water

Accelerated short-term leach tests in a laboratory are neccessary in order to estimate, with reasonable accuracy, the long-term leaching behavior of high-level waste glass. In the present study, static leach tests of an SRL-165 high-level waste glass were carried out in deionized water at two different glass-surface-area to solution-volume ratios (SA/V-ratio), namely 0.85 and 0.079 cm^?1 at 90°C, and 0.85 cm^?1 at 40°C.

First, an equation was examined which related Si-concentrations with time, temperature and SA/V-ratio under the present static conditions. The parameter determined at 90°C, 0.85 cm^?1 can be used to calculate the Si-concentration at 40°C, 0.85 cm^?1. Second, at the low SA/V- ratio of 0.079 cm^?1, the concentrations of Ca and Mg in the leachates peaked and then decreased a little. The equation used above does not explain the variation of the concentrations of Ca and Mg at a low SA/V-ratio. The precipitation of Ca and Mg onto the glass surface is probably caused by the adsorption efficiency of the surface layer or the formation of crystalline materials at the low SA/V-ratio of 0.079 cm^?1. Third, the in-depth profiles of some elements obtained by secondary ion mass spectroscopy (SIMS) were qualitatively in agreement with the results of solution analyses. This indicates the particular usefulness of SIMS for analyzing leaching behavior of the glass in in-situ burial studies where solution analyses are often impractical.     

巴音戈壁盆地塔木素地区黏土岩地质特征研究

黏土岩是高放废物地质处置库重要的候选围岩之一。通过野外地质勘查,查明塔木素地区黏土岩产状平缓、分布广泛、沉积环境稳定。采用薄片鉴定、X射线衍射及扫描电镜分析等方法,研究了该地区黏土岩的岩石学和矿物学等特征,结果表明,岩石具泥质结构、致密块状构造,黏土矿物主要为高岭石、伊利石等。研究初步认为该地区黏土岩基本满足高放废物地质处置库围岩的要求。     

Feasibility Study on Transportation Techniques Employing Air-Bearing System for Pre-Assembled Waste Package at Drift Tunnel of HLW Repository

Full-scale tests were performed to evaluate the technical feasibility of a transport system with air-bearings at the underground HLW disposal tunnel for pre-assembled heavy disposal packages, which consist of a waste package and buffer material. Transport conditions in the disposal tunnel, such as roughness and unevenness of the curved surface, make it difficult to achieve smooth movement using the commercial airbearing transport system. In order to evaluate the applicability of the air-bearing transport system to such conditions, tests using a full-scale test device (modified package) and simulated tunnel surface were conducted. Based on the tests, the applicability of this transport system to a disposal tunnel was confirmed.     

Comparison of Nuclear Waste Glass Leached in Natural Groundwater at 14°C with That in Synthesized Groundwater at 70°C

The influence of fast neutron irradiation was studied for CdTe radiation detectors in the range of fluence 1.0 × 10⁸-1.8 × 10¹¹ n/cm². The effect of γ-ray heavy irradiation toward the detector was also investigated for the comparison. Americium-241 and ¹³⁷Cs γ-ray spectra measured before and after irradiation were compared to examine the change of the detector performance. A pulse height and a rise time of a radiation signal were simultaneously measured in order to evaluate the transport property of both elections and holes. Peak shift toward lower energies was observed in the ²⁴¹Am γ-ray spectrum after fast neutron irradiation. Electron μτ product showed large decrease with increasing the neutron fluence, while the one for holes remained unchanged. For the γ-ray irradiation, the spectrum shape of ¹³⁷Cs changed due to the influence of carrier detrapping. Experimental results support that the electron-trapping center generated by fast neutrons degrades the detector performance of the CdTe detector.     

Self-Limiting Power Excursion Characteristics of Light Water Reactor,(II)

The power excursion characteristics of a water-moderated UO₂ fuel reactor were investigated by pulse operation tests on the Hitachi Training Reactor. A series of pulse operation tests were performed without mishap with reactivity insertions up to 1.20% Δk/k, corresponding to a reactor period of 15 msec. With a reactivity insertion of 1.20% Δk/k, the peak power and energy release to the time of peak power were found to be restricted by the Doppler effect to 118 MW and 4.1 MW-sec respectively. Comparison were made between experimental and calculated values of peak power and energy for various published resonance integral temperature coefficients.