可移动式高分辨率分段γ扫描现场测量装置的研制

描述了１台用于核设施、核材料现场测量的可移动式高分辨分段γ扫描装置。本装置用７５Ｓｅ和１６９Ｙｂ作为透射源测量样品对γ射线的透射率，采用近立体角三维自吸收校正模型计算样品自吸收校正系数ＣＦ（ＡＴ），较准确计算出样品对γ射线的自吸收校正量。本装置适合于准确测定中低密度非均匀核返料和核废物中核材料含量或裂变产物的含量，对２３５Ｕ硝酸铀酰均匀介质的盲样，测量结果与控制电位库仑测定的标准值之偏差小于１．４％。     

注塑机安全解决方案

随着国内注塑机行业的快速发展与国标的出台,注塑机生产厂家亟需获知如何使国产注塑机满足国标乃至国际标准,从而从根本上提高国产注塑机的竞争力与附加值。本文依据注塑机国标GB 22530,详细阐述了注塑机的典型危险源以及如何通过本质安全设计、增设防护装置等方式来降低风险,满足相应性能等级的要求,并提供了完整的产品方案。     

Verification of U mass content in nuclear fuel plates by an absolute method

Nuclear Safeguards is referred to a verification System by which a State can control all nuclear materials (NM) and nuclear activities under its authority. An effective and efficient Safeguards System must include a system of measurements with capabilities sufficient to verify such NM. Measurements of NM using absolute methods could eliminate the dependency on NM Standards, which are necessary for other relative or semi-absolute methods. In this work, an absolute method has been investigated to verify the ²³⁵U mass content in nuclear fuel plates of Material Testing Reactor (MTR) type. The most intense gamma-ray signature at 185.7 keV emitted after -decay of the ²³⁵U nuclei was employed in the method. The measuring system (an HPGe-spectrometer) was mathematically calibrated for efficiency using the general Monte Carlo transport code MCNP-4B. The calibration results and the measured net count rate were used to estimate the ²³⁵U mass content in fuel plates at different detector-to-fuel plate distances. Two sets of fuel plates, containing natural and low enriched uranium, were measured at the Fuel Fabrication Facility. Average accuracies for the estimated ²³⁵U masses of about 2.62% and 0.3% are obtained for the fuel plates containing natural and low enriched uranium; respectively, with a precision of about 3%.     

核保障无损分析设备中图形界面软件的研制

首先介绍了图形界面技术的一般性方法,提出了实际应用系统中正文构造、多层次下拉式菜单、多窗口弹出式交户图形信息显示等人机接口基础模块的设计技术。最后给出在核保障无损分析设备中的应用实例,表明该软件系统在界面友善性、谱形动态活显及打印描谱等方面均优于目前国际上的通用软件,如美国EG&G ORTEC公司的MCA产品。本文的程序设计方法,既适用于核谱获取及处理系统,其有关算法也适用于一般性微机图形界面的设计。     

核安全保障非破坏性分析研究与发展（Ⅰ）

本文阐述了国外核材料安全保障非破坏性分析研究与发展的最新情况,包括技术开发的国际合作概况和部分重要研究课题的进展:(1)γ能谱法测定钚同位素丰度;(2)钚溶液的浓度测量技术;(3)混合式K-边界密度计/XRF;(4)乏燃料核查仪器;(5)分段γ吸收扫描法;(6)无源中子符合计数法测定钚含量;(7)有源中子质询法。     

Consequences of the fragmentation of global environmental governance: the case of safeguards in the financing of large dams

This article uses a broad framework to analyse the fragmentation of global governance architectures, and explores the consequences of such fragmentation with specific regard to the stringency of safeguards standards in the financing of large infrastructure projects, using the example of large dams. Drawing on original research, the author shows differences in safeguards stringency at the level of institutional policies, then at the level of projects financed by Public Financing Institutions (PFIs). Safeguards stringency differs substantially between different PFIs. There is fragmentation between multilateral and bilateral PFIs; and fragmentation among bilateral PFIs. The reasons are differences in coordination mechanisms among different PFIs, and diverging interest group pressure on PFIs. The article explores the key consequences of this fact for fragmentation of global governance. Key consequences are likely for ‘ambition’ (the ability of leaders to go further on the ‘standards’ they wish to set); and ‘equity’ (the ability to offer tailored solutions for specific regions or countries).     

Global identification and monitoring of UF6 cylinders

Abstract

An expansion of global commerce in nuclear material will accompany the forecast worldwide renaissance in nuclear power. The increased commerce amplifies the risk that uranium hexafluoride (UF₆) in cylinders could be lost as a result of an accident or mishandling, stolen by non-state actors (e.g. terrorists), or diverted by nation states/governments. While there are very few problems with UF₆ cylinder shipments, the complicated logistics of international truck, rail and sea transport can increase difficulty in locating shipments at any given time and significantly delay transport and reporting. The recent revelations about undeclared enrichment plants, such as Qom in Iran and the newly revealed 2000-centrifuge plant in North Korea, have underscored the threats of undeclared production of low enriched uranium and the attempted diversion in which low enriched uranium could be transported to a relatively small, clandestine plant and enriched up to weapons grade (or weapons usable) highly enriched uranium in a short period of time. A global system of registering, identifying and monitoring UF₆ cylinders would provide more robust and timely assurance that no UF₆ in legitimate nuclear commerce is mishandled or diverted. The Office of Nonproliferation and International Security of the US Department of Energy’s National Nuclear Security Administration (NNSA) has formed a multilaboratory team to focus on universal UF₆ cylinder identification and global monitoring. The team produced an overview report discussing the current situation and potential solutions and identified future tasks that fall into three general categories. The first category involves policy initiatives to bring together all relevant stakeholders, i.e. facility operators and industry, state regulators and government agencies, international inspectorates and technology developers, to reach consensus on universal identification and the importance of cylinder monitoring. Such policy level discussions would include standardisation of components, protocols and procedures. The second category concerns a deeper investigation of the concepts involved, reflected in the research and publication of papers and technical reports. Such background work is merely the ‘tip of the iceberg’ but may facilitate acceptance of a global regime by the stakeholders. The third category involves technology assessments and field trials to enable the development of theoretical concepts into practical approaches. This paper gives an overview of the progress to date and examines the next steps for governments and international agencies (from the policy side) and industry and national laboratories (from the technology and development side).     

直面保障措施,促进国内产业健康发展

保障措施是WTO规则允许的成员国用以合理保护国内产业的行政手段之一。结合WTO《保障措施协议》的有关条款，从我方作为WTO允许的保障措施的实施方和被实施方2个方面，阐述了我方需给予重视的环节。最后指出保障措施的运用是一个不断平衡自身得与失的过程，它给了相关行业一个附加的保护时间。但毕竟只是权宜之计，想方设法提高自身的实力才能长治久安。     

便携式铀丰度仪的研制

研制了用于测量新燃料组件或新燃料元件￣（２３５）Ｕ丰度的便携式铀丰度仪。仪器采用带￣（２４１）Ａｍａ源的φ２０×２０Ｎａｌγ探头，具有高压自控稳定的特性，仪器的电子学线路全部密集安装在３２６×１０６×１７６的枪式箱体内，具有小型、轻便的特点。仪器在测新燃料组件中￣（２３５）Ｕ丰度时，测量的精度好于±２．０％，同时可扫描测出组件中的装料长度。     

核保障视察仪器与方法

简述了核保障视察的种类、仪器设备及方法。概要介绍了核保障视察技术的发展动态。