交联聚乙烯HIC在美国处置场应用实践及对我国的启示

简要介绍了从美国引进的交联聚乙烯高完整性容器(HIC)及其在美国Clive和Barnwell处置场的应用实践,对交联聚乙烯HIC在我国应用中存在的自由水含量、累积剂量、辐照分解气体、外包装等主要问题和解决思路进行了探讨,期望能对交联聚乙烯HIC在我国的处置方案的选择提供一些参考。     

Treatment and geological disposal of waste from NET pre-design

Within the European Fusion Technology programs Studsvik RadWaste AB has performed studies on fusion waste treatment and disposal for several years. This paper deals with the treatment and geological disposal of radioactive waste from NET operation and decommissioning. Results from calculations on radioactive waste fluxes for the operation and decommissioning of NET are reported. The calculations are based on the NET predesign report published 1993 and include results for the exchangeable in-vessel and external parts of the machine as well as permanent reactor components. Different aspects of treatment, packaging, transportation, and interim storage of the waste are discussed. The volumes of waste conditioned for final disposal are preliminarily quantified, according to German and Swedish scenarios for radioactive waste disposal. A total repository volume of approximately 45,000 m³ is required in the German Scenario and 35,000 m³ is required in the Swedish Scenario. Results from dose rate calculations for NET waste in final repositories are presented for the Swedish Scenario. This work was financially supported by the Swedish Natural Science Research Council (NFR) and the European Atomic Energy Community, under an association contract between Euratom and Sweden.     

Failure model and Monte Carlo simulations for titanium (grade-7) drip shields under Yucca Mountain repository conditions

A failure model was developed for the titanium alloy drip shield proposed for the Yucca Mountain nuclear waste repository. The degradation modes considered are hydrogen-induced cracking (HIC) and general aqueous corrosion, processes which are inextricably linked. Failure by HIC is controlled by the environment, the corrosion rate, the material properties, and the hydrogen absorption efficiency which is assumed to decrease parabolically with time. This model includes both oxygen and water reduction coupled to corrosion, and allows for the release of the absorbed hydrogen as the alloy containing the hydrogen converts to oxide. Monte Carlo simulations were employed to predict drip shield lifetimes, and to investigate the effects of the hydrogen absorption efficiency, the critical HIC concentration, the corrosion rate, and the fraction of corrosion supported by water reduction, on the susceptibility of the material to HIC.     

高整体容器在我国放射性废物管理中的应用分析

对3种材料高整体容器(HIC)进行简述,介绍交联聚乙烯HIC处理工艺及规格对于传统水泥固化处理工艺的优势与不足。对交联聚乙烯HIC在工程应用中的废物装填及吊装环节、运输环节、处置环节等几个方面需要重点关注的问题进行分析,对于设计中需要解决的问题提出解决的方向,并简述了HIC应用方面后续需要继续开展的工作。     

Development of DETAC and its application to the hydrogen detonation analysis

In this study, a numerical analysis code (DETAC, Detonation Analysis Code) for hydrogen detonation during the reactor severe accident was developed using Fortran 90 language, and the simulation was performed for the hydrogen detonation. A global-chemistry model was adopted to simulate the chemical reaction. The Euler equations were solved using third-order Runge-Kutta method with fifth-order weighted essentially non-oscillatory scheme handling the convection flux. Afterward, the hydrodynamics solver was verified by comparison of predicted results and exact solutions of four cases of shock tube problems. A hydrogen detonation in a pipe was simulated to verify this code by comparing the results with the classical C-J theory. Furthermore, this code was applied to the hydrogen detonation analysis in the compartment of BWR building. Two cases with different ignition locations were analyzed in this paper and the maximum pressure of these cases were 7.5 MPa and 8.0 MPa, respectively. The pressure and the temperature during detonation were affected by the ignition location. The results indicated that the possibility of reactor building destruction exists if the hydrogen detonation occurs.     

钠水反应试验系统中小泄漏钠水反应氢气分布特性

蒸汽发生器是钠冷快堆的关键设备之一，其传热管破裂引发的钠水反应会产生大量氢气及热量，危害钠冷快堆的安全运行。本文基于VOF多相流模型，在钠水反应试验系统内开展中小泄漏钠水反应工况的数值分析，获得了高压反应釜内氢气在钠水反应下的三维空间分布特性和迁移特性。结果表明：高压反应釜内氢气的迁移特性受钠液流速影响，氢气在整个循环环路的迁移特性主要受水泄漏量控制。通过设置灵敏度为0.005 ppm的氢计，获得了环路不同区域检测到氢气的最快特征时间。     

局部空间内氢气爆炸程序开发及应用

针对反应堆安全壳或厂房局部空间内氢气爆炸过程,利用Fortran 90语言开发了氢气爆炸数值分析程序。采用单步反应模拟氢气与空气的化学反应,采用5阶精度的WENO求解对流项,时间步进采用3阶精度的龙格-库塔方法,对局部二维空间内氢气/空气/水蒸气预混气的爆炸过程进行了数值模拟。采用开发的程序计算了两种典型的激波管问题以验证程序的准确性,并用该程序分析了带隔间的沸水反应堆厂房局部空间内的氢气爆炸过程。计算结果表明：爆炸过程中最大的压力峰值来源于冲击波与反射波之间的碰撞,最大的冲击波压力和温度高达7.5 MPa和3 245 K。由此可得,安全壳内的氢气爆炸过程可能会威胁到安全壳的完整性,导致放射性物质释放。     

高放玻璃多重屏障介质多因素耦合处置方法研究

地下水透过多重屏障介质与高放玻璃固化体直接接触后,放射性核素会从固化体中释放,因此成为高放废物处置库安全评价的源项。为更精确地预测玻璃固化体长期处置行为,本文考察了围岩、回填材料等因素对模拟高放玻璃固化体中各关键元素浸出的影响,实验处置温度为90 ℃,模拟高放玻璃固化体依据德国配方制备。结果表明,围岩对玻璃体中不同元素的阻滞作用有所差异。B、Re和U的浸出浓度在二长花岗岩中最大;膨润土含水量高时,玻璃体中元素释出量大;而含水量低时,释出量小;在膨润土中添加5%的素玻璃粉,对玻璃的腐蚀有抑制作用。     

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.     

Recent activities in the field of nuclear waste management

Buffer construction using bentonite pellets as filling material is a promising technology for enhancing the ease of repository operation. In this study, a test of such technology was conducted in a full-scale simulated disposal drift, using a filling system which utilizes a screw conveyor system. The simulated drift, which contained two dummy overpacks, was configured as a half-cross-section model with a height of 2.22m and a length of 6.0 m. The average dry density of the buffer obtained in the test was 1.29 Mg/m³, with an angle of repose of 35 to 40 degrees. These test results indicate that buffer construction using a screw conveyor system for pellet emplacement in a waste disposal drift is a promising technology for repositories for high level radioactive wastes.     

Simulation of a neutron scattering method for measuring void fraction in two-phase flow

Experiments have indicated that fast/epithermal neutron scattering techniques are attractive for void fraction measurement in two-phase flow. Some of these experiments have been simulated by Monte Carlo neutron transport calculations. The simulations predict results in agreement with the measurements. This suggests that the experimental technique has a sound theoretical basis, and that numerical simulations may be used to design experimental setups for different applications.     

Analysis of hydrogen risk mitigation with passive autocatalytic recombiner system in CPR1000 NPP during a hypothetical station blackout

Hydrogen safety has attracted extensive concern in severe accident analysis especially after the Fukushima accident. In this study, a similar station blackout as happened in Fukushima accident is simulated for CPR1000 nuclear power plant (NPP) model, with the computational fluid dynamic code GASFLOW. The hydrogen risk is analyzed with the assessment of efficiency of passive autocatalytic recombiner (PAR) system. The numerical results show that the CPR1000 containment may be damaged by global flame acceleration (FA) and local detonation caused by hydrogen combustion if no hydrogen mitigation system (HMS) is applied. A new condensation model is developed and validated in this study for the consideration of natural circulation flow pattern and presence of non-condensable gases. The new condensation model is more conservative in hydrogen risk evaluation than the current model in some compartments, giving earlier starting time of deflagration to detonation transition (DDT). The results also indicate that the PAR system installed in CPR1000 could prevent the occurrence of the FA and DDT. Therefore, HMS such as PAR system is suggested to be applied in NPPs to avoid the radioactive leak caused by containment failure.     

Characteristics of a Geological Disposal System for the Increasing Burn-up of Spent Nuclear Fuel in Korea

The characteristics of a geological disposal system that can accommodate increasingly higher burn-up levels of spent fuel were assessed based on the Korea reference disposal system concept. First, a status investigation that included a projection of spent fuel quantity versus burn-up was carried out to demonstrate the trend toward higher burn-up levels. Next, the main features of the Korea reference disposal system were introduced. Finally, the disposal tunnel length, excavation volume, and raw materials (e.g., a cast insert, copper, bentonite and backfill) necessary for a disposal system were comprehensively analyzed to define the characteristics and overall effects on geological disposal at increasingly higher burn-up levels. Our study determined that it is reasonable to use a canister containing 4 spent fuel assemblies with burn-up levels up to 50GWD/MTU, while a canister containing 3 spent fuel assemblies can accommodate burn-up levels beyond 50GWD/MTU. A remarkable increase of 33% in disposal tunnel length and that of 30% in excavation volume were observed as the burn-up increased from 50 to 60GWD/MTU. However, this was offset by a reduction of 17% in raw materials used in canister fabrication. Therefore, it seems that spent fuel at increasingly higher burn-up levels is not a serious concern for deep geological disposal in Korea.     

乏燃料处置的必要性及其处置库环境化学行为

为了确保核燃料循环的安全性，不宜处理的乏燃料也应该同玻璃固化体一样作为高放废物进行深地质处置。本文综述了一些前期工作，归纳了空气侵入和水的辐解产生氧化性产物是导致乏燃料UO2基体氧化溶解的主要因素; 核燃料浸出实验结果显示铀和锕系镧系元素每天的浸出量是相应核素总量的1/107，比裂变产物的浸出速率小一个数量级。铁金属被各国选为高放废物处置容器材料的原因是其低价格、高强度和优秀的还原能力。在最不利的地下水侵入深地质处置库、近场处置容器防腐层破损的情景下，铁容器材料表面与地下水反应产生氢气，氢气通过还原反应消耗辐解产生的氧化性自由基和分子, 并能还原乏燃料表面的U（Ⅳ），大幅度减缓乏燃料的腐蚀和溶解；乏燃料中裂变产物贵金属合金颗粒对氢气有催化作用；处置容器表面铁金属能还原沉积溶解的多价态核素U（Ⅵ）、Np（Ⅴ）、Tc（Ⅶ）、Se（Ⅳ）和Se（Ⅵ）。希望本文对我国确立以铁基金属为处置容器材料的包括乏燃料在内的高放废物深地质处置概念有参考作用。     

Effects of ferromagnetic components on energetic ion confinement in ITER

By using a fully three dimensional magnetic field orbit-following Monte-Carlo code, the energetic ion confinement was investigated for the current conceptual design of the ferromagnetic components in ITER which will be employed for reducing the toroidal magnetic field (TF) ripple. The ferromagnetic insert is effective in the reference standard scenario with Q = 10 (Scenario No. 2) and steady state scenario with Q = 5 (Scenario No. 4) to improve the energetic ion confinement. Over-compensation appears at half of the full toroidal magnetic field and its effect becomes stronger when the quantity of the ferromagnetic insert is increased in order to more reduce the TF ripple at the full toroidal magnetic field. Though the current design is acceptable, whether to increase the ferromagnetic insert to achieve lower TF ripple amplitude at the full field operation depends on how prospected are possibilities of lower field operations. Planned test blanket modules do not induce large loss (<1%) at the full field in Scenario No. 4. At the half field, however, the loss reaches ∼10% for the alpha particles due to localized large TF ripple.     

腐殖酸对Np胶体行为的影响

在模拟高放废物深地质处置的低氧低浓条件下,探讨用膜过滤法研究Np胶体行为的可行性。实验研究结果表明:无腐殖酸存在时,在pH=1～13条件下,无机离子对237Np的测定无明显影响,237Np的液闪探测效率可达100%;增加闪烁液用量可消除腐殖酸对237Np的淬灭效应,过滤器对237Np的吸附可忽略不计,说明将过滤法应用于Np的胶体行为研究准确、可靠,操作简便。应用该方法对Np的不同价态和腐殖酸存在下的胶体行为进行了研究。Np(Ⅴ)无明显胶体行为,Np(Ⅳ)以真胶体形态存在,其浓度显著影响胶体行为;腐殖酸与Np(Ⅳ)能形成假胶体,从而提高了Np(Ⅳ)在溶液中的含量,有利于Np的迁移。腐殖酸是核素迁移研究必须考虑的重要影响因素。     

谈谈高整体容器

阐述了高整体容器当今受重视的原因,并对几种高整体容器进行比较,介绍了国际上几类高整体容器构造和特性,高整体容器的试验方法,最后对我国研发和制造高整体容器提出了意见和建议。     

Numerical simulation of single bubble condensation in subcooled flow using OpenFOAM

The single condensing bubble behavior in subcooled flow has been numerical investigated using the open source code OpenFOAM. A coupled Level Set (LS) and Volume of Fluid (VOF) method (CLSVOF) model with a phase change model for condensation was developed and implemented in the code. The simulated results were firstly compared with the experimental results, they were in great agreements, and thus the simulation model was validated. The validated numerical model was then used to analyze the condensing bubble deformation, bubble lifetime, bubble size history, condensate Nusselt number and other interesting parameters with different variables in subcooled flow. The numerical results indicated that the initial bubble size, subcooling of liquid and system pressure play an important role to influence the condensing bubble behaviors significantly and bubble will be pierced when the subcooling and initial diameter reach a certain value at the later condensing stage. The bubble diameter history and condensate Nusselt number were found in good agreement with the empirical correlation. The drag force coefficient was predicted well by introducing a reduced drag coefficient.     

谈谈高整体容器

阐述了高整体容器当今受重视的原因，并对几种高整体容器进行比较，介绍了国际上几类高整体容器构造和特性，高整体容器的试验方法，最后对我国研发和制造高整体容器提出了意见和建议。     

Influence of atmospheric gases on the treatment of miscellaneous solid wastes by plasma melting technology

The material properties of the treated waste forms and the behavior of radionuclides found in the plasma melting tests of simulated miscellaneous solid wastes (iron, fly ash and wood) with cold tracers were examined by using different heating atmospheric gases. The material properties were changed with increasing iron oxide content in the slag layers by changing atmospheric gases. The results showed a homogeneous distribution of cold tracers and low leaching rate of it from the treated waste forms appropriate for shallow land burial site disposal in every atmospheric gas. The high residual rate of Cs in the slag layers (about 70%) was obtained in the plasma melting process except the extremely high reductive atmospheric conditions.