放射性物质的大气弥散

通过仿真计算,分析了核事故发生放射性物质泄漏期间,在各种大气稳定度条件下,相对于不同地理环境的烟羽弥散趋势,以及事故泄漏周围区域放射性物质的时间积分浓度分布情况。模拟的结果很好,符合放射性物质在近地面轴线上的浓度分布情况,为核事故应急提供了有利的依据。     

Excluded,exempt and LSA quantities for transport of NORM radioactive material

Abstract

The main objectives of this research work are the determination of the quantities of naturally occurring radioactive material (NORM) that can be excepted from the International Atomic Energy Agency (IAEA) Transport Regulations, the establishment of quantities of NORM that can be transported in excepted packages as well as the provision of sound basis for the establishment of limiting values for the classification of NORM as low specific activity material I raw for transport purposes, in order to compare with the actual transport limits established in the IAEA Transport Regulations for this type of material.     

放射性物品运输容器试验验证经验总结

我国放射性物品运输实施分类监管。试验是验证放射性物品运输容器安全性能最直接的手段。本文对放射性物品运输容器的试验要求与检测方法进行了综述,并对运输容器安全性能试验的经验进行了总结。     

放射性物品运输容器防脆性断裂安全设计方法探讨

本文主要介绍了基于断裂力学的运输容器防脆性断裂安全设计,重点研究了防脆断条件中应力强度因子的计算方法。经分析,可以得出如下结论:RCC-M第Ⅰ卷附录ZG中的应力强度因子计算考虑了应力非线性分布和塑性区的影响,考虑因素比较全面,推荐采用。     

中国实验快堆气载放射性物质释放路径研究

中国实验快堆是我国建设的第一座钠冷快中子反应堆,2014年实现满功率运行。本文主要阐述中国实验快堆气载放射性物质的来源、堆内迁移以及向环境释放的路径,得出正常工况以及事故工况下放射性物质通过哪些路径向环境排放,目的是有助于了解中国实验快堆通过哪些路径对环境产生放射性影响,从而建立并保持对放射性危害的有效防御,以保护人员、社会和环境免受危害,防止工作人员和公众接受超剂量的放射性照射。     

Packaging and security of radioactive material

Abstract

Elastomers are widely used as the main sealing materials for containers for low and intermediate level radioactive waste and as an additional component to metal seals in spent fuel and high active waste containers. The safe encapsulation of the radioactive container inventory has to be guaranteed according to regulation and appropriate guidelines for long term storage periods as well as for temperatures as low as ?40°C during transport. Therefore, the understanding of failure mechanisms that lead to leakage at low temperatures is of high importance. It is known that the material properties of elastomers are strongly temperature dependent. At low temperatures, this is caused by the rubber–glass transition (abbreviated: glass transition). During continuous cooling, the material changes from a rubber-like entropy elastic to a stiff energy elastic behaviour, which allows nearly no strain or retraction. Hence, rubbers are normally used above their glass transition, but the minimum working temperature limit is not defined precisely; this can cause problems during the above noted applications. Therefore, the lower operation temperature limit of elastomer seals must be determined in dependence of the material properties. Differential scanning calorimetry (DSC) and dynamic mechanical analysis (DMA) are combined with standardised measurements to determine the compression set according to ISO 815. To reduce the test time of the standard tests, a faster technique than normally used was developed. Additionally, the breakdown temperature of the sealing function of complete O ring seals was measured in a component test set-up to compare it with the results of the other tests. The experimental set-up is capable of measuring the leakage rate at low temperatures by the pressure rise method. A fluorocarbon rubber (FKM) was selected for this investigation as it is often used for radioactive waste containers. The materials (seals and test sheets) were purchased from a commercial seal producer.     

热熔压敏卷材清除放射性污染粉尘的试验研究

为了实现介质表面放射性污染粉尘的快速去污,提出一种应用热熔压敏卷材清除表面污染粉尘的方法。通过对热熔压敏胶黏剂与卷材基布的筛选,设计和制备了一种热熔压敏去污卷材,分别采用过100目、20目标准筛的粉尘模拟核爆落下灰和放射性污染颗粒物,对热熔压敏去污卷材进行模拟去污试验。试验结果显示,所制备的热熔压敏卷材在140 ℃、施加25 kPa以上压强时,对不锈钢表面的模拟放射性污染粉尘和颗粒物的单次去污率均在80%以上,最高达到92.5%。验证了热熔压敏卷材对表面放射性污染粉尘的去污效果,可为工程应用提供参考。     

建筑材料中放射性物质限制标准的若干建议

对于建材中放射性物质的限制，建议制订统一的国家标准，适当降低^226Ra的限制值，对用于建材生产的工业废渣本身也应该进行比活度限制，对超过限值的产品必须从严控制，建材产品在销售前应该进行放射性物质比活度的强制检测。     

国际原子能机构放射性物质运输安全标准发展回顾

国际原子能机构(IAEA)有5个安全标准委员分别负责相关领域安全标准制修订工作,运输安全标准委员会(TRANSSC)是其中之一,主要负责与放射性物质运输安全相关标准的制修订工作。文章介绍了IAEA放射性物质运输安全标准发展、TRANSSC的简要情况、标准制修订流程以及近年来SSR-6等文件修订情况,提出了我国参与IAEA运输安全标准制修订工作的建议。     

Terrorism and maritime shipment of nuclear material

Abstract

Opponents of the nuclear industry often claim that material in transit is vulnerable to attack by terrorist groups who might seek to take the cargo and make a bomb, or otherwise cause a radiological incident. This paper lays out a range of conceivable objectives or attack scenarios in the context of maritime transportation and examines these in the light of what is known of the relevant security arrangements. It concludes that these arrangements provide a very substantial deterrent to any attempt at diversion or sabotage and that any such attempt would have little prospect of success, beyond the immediate media impact of whatever might have occurred.     

Development of international guidelines for shipment security of radioactive materials

Abstract

In October 2003 a weeklong IAEA Technical Meeting developed a set of guidelines for providing security to consignments of radioactive materials in transport. These guidelines will be published in an IAEA TECDOC Security in the Transport of Radioactive Material. The guidelines produced reflect consideration of many influences and concerns that currently revolve around the potential for terrorist use of radioactive material for malevolent ends. The influences discussed here include: public perception of hazard and concern that new requirements will further limit global shipping capability, international efforts to control sealed sources, national efforts to increment protection on selected materials, the basis for exemption of materials, concern for cost impacts of overly broad requirements, questions on how to adjust requirements for a national threat assessment and issues relating to consistency within the international community on security needs.     

高活度废放射源整备屏蔽材料(沙子)性能研究

针对高活度废放射源整备建立了可移动废放射源整备屏蔽实验装置,利用该装置,从工程运用角度开展了忻州沙的粒径、密度测量和屏蔽实验,筛选出了适合废放射源整备使用的特定类型沙子。研究结果显示:采用厚度150 cm饱和含水忻州建筑沙作为屏蔽材料,可确保1 000 Ci ⁶⁰Co废放射源整备时在屏蔽装置外产生的剂量率小于0.03 mSv/h。     

A simple method with imaging plates for examination of soil contaminated with radioactive caesium

A simple and convenient system with imaging plates (IPs) was well constructed for the radioactivity examination of soil contaminated with radioactive caesium. A set of two IP strips was vacuum-sealed with thin polyethylene film to prevent the IP strips from direct contacting soil and from being moisturized. In the examination of radioactive soil, a stainless steel pipe including this IP strip monitor was put into the ground and then it was kept in a lead container after being pulled out of the ground for the reduction of the surrounding gamma-ray background. In addition, a sensitive reader was well made for the measurement of the photostimulated luminescence through the scanning of a laser beam on the IP strip. It was confirmed from experiments on actual radioactive-caesium-contaminated soil that the IP strip monitor with the reader effectively detected beta-rays from radioactive caesium and could be satisfactorily used for the examination of radioactive soil.     

Solidification of spent radioactive organic solvent by sulfoaluminate and Portland cements

The solidification of simulated spent radioactive organic solvent, tri-butyl phosphate/kerosene, was investigated by emulsification–solidification method using sulfoaluminate cement (SAC) and Portland cement (PC). Zeolite, calcium hydroxide and MR-1 type emulsifier were mixed into the cement blends for improving the performance of solidified waste forms (SWF). The properties of SWF were evaluated in terms of mechanical strength, leachability and mineral phase analyses. The hydration products of SWF were characterized by X-ray diffraction (XRD). The experimental results showed that the 28 d compressive strengths of SAC solidified waste forms (SACF) and PC solidified waste forms (PCF) were 14.23 and 19.07 MPa, respectively. Leaching sequence of three radionuclides in two kinds of SWF is Cs⁺ > Sr²⁺ > Co²⁺. Compared with PCF, SACF had better performance in preventing nuclides Co²⁺ and Cs⁺ from leaching to the environment. The XRD patterns suggested that simulated spent radioactive organic solvent and emulsifier in SWF did not obviously change the hydration products of the two cements (SAC and PC).     

近场核素释放率对缓冲材料参数的敏感性研究

缓冲材料对高水平放射性废物(高放废物)地质处置库的安全至关重要。本文在处置库关闭后预期演变情景分析的基础上,运用蒙特卡罗随机模拟方法,对缓冲层厚度、缓冲材料密度、核素在缓冲材料中的分配系数这三个参数进行敏感性分析。结果表明,处置库关闭后1 000 a内,近场核素释放率对缓冲层厚度较敏感,超过1 000 a 后敏感性较低;近场核素释放率对缓冲材料密度不敏感;核素在缓冲材料中的分配系数不断提升的情况下,对应的参数敏感度也逐渐加大。上述敏感性分析结果可为缓冲材料工程设计提供参考。     

地球化学工程学在放射性废物处置中的应用

介绍了应用地球化学工程学治理环境的基本依据,常用的放射性废物处置工程模式和工程屏障的功能,并以某放射性废物处置场地球化学工程屏障物料研究为例,说明地球化学工程学在放射性废物处置中的应用。研究结果表明,采用地球化学工程学方法来改良放射性废物处置场址的天然缺陷,可大大提高放射性废物处置的安全性。     

放射性废物焚烧技术的发展历程和展望

焚烧是放射性废物的主要处理技术之一,同常规废物焚烧技术相比,放射性废物焚烧技术更关注对放射性核素的截留效果、系统的辐射安全和对废物的适应能力。随着废物特性的变化、环保要求的日益严格,焚烧技术也在不断的革新和改进,对塑料、橡胶和树脂等高分子聚合物适应性更强的第三代焚烧技术已成为主流,包括热解焚烧、蒸汽重整焚烧以及等离子体焚烧,分别适用于不同的废物类型。未来放射性废物焚烧技术的发展趋势以整体经济性和满足环保要求为前提,尽量提高废物的整体减容效果,对多种废物的兼容处理,并为满足特殊废物的处理要求开发针对性的焚烧技术。     

放射性废物处置安全若干进展

结合2005年放射性废物处置安全国际大会反映出来的放射性废物处置安全领域的最新进展,介绍了全球放射性废物安全框架、废物处置安全战略、安全方案、地质处置设施安全、近地表处置设施安全、中等深度废物处置方案和公众沟通等方面的若干新进展和新观点。     

放射性检测领域的能力验证

放射性检测领域长期以来没有能力验证提供者,从事放射性检测工作的人员对实验室间比对和能力验证的认识不够深入。能力验证的关键过程包括能力验证物品的制备及其均匀性和稳定性检验、包装及分发、参加者结果的评定等内容。其中参加者结果的评定可参考IAEA的评定方法,更为全面可靠。     

放射性废树脂处理技术工程应用的选择

本文介绍了目前世界上放射性废树脂的各种处理方法,研究分析了各种处理方法的优缺点,在进行全寿期成本分析的基础上提出工程应用的选择原则及建议。