便携式CZT探测器铀富集度测量装置的实验研究

本实验采用eVProduct公司生产的共屏栅结构CdZnTe（CZT）探测器，建立了一套便携式铀富集度测量装置（图1）。该装置由CdZnTe探测器、屏蔽准直体、Inspector2000谱仪和一台笔记本电脑组成，采用VisualBasic语言对Genie2000系统进行二次开发，实现装置的控制操作和实时测量分析。     

CZT探测器的峰形拟合

作为一种中等分辨率且能在常温下使用的小型探测器，CZT特别适用于便携式现场测量设备中。由于载流子传输过程中发生电荷不完全收集及空穴俘获等效应，致使CZT探测器输出谱的全能峰偏离了理想的高斯峰形而伴有显著低能拖尾。对于标准包装的含铀材料，易于采用235U的186keY单一能峰进行解谱分析（丰度计原理）；对于不规则样品，在包装物对低能X和γ射线吸收不太显著的情况下，CZT能谱，特别是低能部分的能峰，相互重叠严重，在解谱过程中需要合适的峰形拟合算法。     

便携式^235U丰度仪的改进与应用研究

对基于ＮａＩ（Ｔｌ）探测器的铀丰度测量原型仪器进行了改进。改进后的仪器可以运用计算机进行在线数据获取。利用标准燃料棒对仪器进行了刻度实验，运用刻度结果对大亚湾核电厂的燃料棒进行了测量，丰度测量值与标称值在－１．０％—２．８％以内符合。     

蒙特卡罗方法在CZT探测器测量乏燃料组件燃耗中的应用

利用碲锌镉（CZT）探测器组成的γ谱探测系统是一种测量乏燃料组件燃耗的较有效的方法。本文利用蒙特卡罗方法,借助于Geant4软件包计算在两种测量方式、多个准直高度条件下组件中¹³⁷Cs和¹³⁴Cs的全能峰探测效率,对测量结果的正确评价分析具有一定意义。另外,采用偏倚抽样方法确定源粒子发射方向,极大提高了CZT探测器全能峰探测效率。     

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。     

铀浓缩厂铀丰度在线监测装置研制

研制了铀浓缩厂产品端UF₆气体²³⁵U丰度在线实时监测装置。该装置由NaI（Tl）探测器、脉冲处理器、压力和温度传感器、管道阀门系统等组成,利用NaI(Tl)探测器对测量容器内气态UF₆中²³⁵U发射的特征γ射线进行测量来得到²³⁵U的量,利用传感器对气体温度、压力进行测量,根据理想气体状态方程得到UF₆气体中U的总量,从而得到²³⁵U丰度。该装置现场应用实验表明：铀丰度在线监测结果相对标准偏差小于1%,与气体质谱计测量结果相对偏差小于1%。     

容器内铀同位素丰度的非破坏探测技术研究

研制了三维样品旋转装置,用PC/FRAM软件分析了通过同轴HPGe探测器采集的铀总量在2—600g、能区在120—1001keV的铀同位素γ射线。建立了高放废物容器内非均匀分布的铀同位素丰度的γ能谱测量方法。对同位素丰度在20%—93%的235U,测量不确定度<0.6%,对238U的测量不确定度<1.3%。     

小型CZT探测器测量浓缩厂铀富集度的实验研究

CZT（CdTe或CdZnTe）是一种新型化合物半导体探测器，用于γ射线能谱测量时，其能量分辨率介于HPGe探测器和NaI（T1）探测器之间。由于这种探测器具有体积小、重量轻、能在室温下长时间工作，易做成小型便携式测量装置等优点，因此，在核保障现场核查中得到了广泛应用。     

铀元件认证技术研究

用高纯锗半导体γ探测器在水平和垂直位置测量了不同铀元件组合系统,采用PC/FRAM分析软件对测量能谱进行了铀丰度分析。结果表明:在铀元件、铀元件外加模拟炸药、铍和铍+模拟炸药三种情况下,分析得到的铀丰度基本一致。分析结果的可信度取决于测量γ能谱的统计涨落。     

重屏蔽条件下铀材料丰度的时间关联测量分析

针对高原子序数物质屏蔽下的铀材料，提出了一种新的技术方法来估算其铀丰度。首先，用D-T中子发生器的14 MeV中子对铀材料及屏蔽层进行主动质询，同时利用裂变射线探测器得到裂变中子/γ射线时间关联测量谱。然后，利用成像探测器建立的断层扫描图像得到铀材料及屏蔽层的几何和材料参数，并调用不同的铀丰度参数进行蒙特卡罗模拟计算，得到时间关联计算谱。最后，寻找与测量谱最匹配的模拟谱，确定铀材料的实际铀丰度。通过对比裂变射线探测器实验测量得到的所有裂变中子/γ射线时间关联谱，结果发现在各种屏蔽层状态下，高浓铀材料与贫化铀材料的时间关联谱均存在显著差异，可用时间关联谱作为区分不同铀材料丰度的重要技术特征；对于相同铀丰度和屏蔽状态下的铀材料，模拟谱与测量谱吻合较好，表明时间关联谱的模拟与实验分析可为铀材料铀丰度的估算提供技术基础。     

Current and Future Problems of the Fuel Supply for Nuclear Power

The structure of the nuclear fuel cycle, consisting of the technological stages of uranium production, refining, enrichment, fabrication of nuclear fuel, and reprocessing of the spent fuel for reuse of the fissioning materials, is examined. Supplying fuel includes supplying fuel for Russian nuclear power plants, propulsion and research reactors, export of fuel for nuclear power plants and research reactors constructed according to Russian designs, export of low-enriched uranium and fuel for nuclear power plants constructed according to foreign designs. The explored deposits of natural uranium, the estimated stores of uranium in reserve deposits, and warehoused stores will provide nuclear power with uranium up to 2030 and in more distant future with the planned rates of development. The transition of nuclear power plants to a new fuel run will save up to 20% of the natural uranium. The volume of reprocessing of spent fuel and reuse of ²³⁵U makes it possible to satisfy up to 30% of the demand for resources required for Russian nuclear power plants. The most efficient measure of the resource safety of Russian nuclear power is implementation of an interconnected strategy at each stage of the nuclear fuel cycle.     

铀同位素标准物质在核燃料系统实验室间比对中的应用

在核燃料系统分析检测实验室间比对活动中，首次开展铀同位素检测项目的设计、策划和实施，选取国家一级标准物质“八氧化三铀中铀同位素标准物质”作为分割样品对，分别采用Z比分数、标准物质测量结果的误差允许限（E）作为能力统计量，对实验室间铀同位素丰度的比对结果进行统计和分析，对测量结果有问题或不满意的情况进行分析和建议。通过首次开展铀同位素项目的比对，拓展了核工业系统实验室能力验证范畴，进一步提高实验室的检测水平，对核燃料循环生产中铀同位素的测量提供了技术基础保障和质量保证。     

利用HPGe铀能谱143～1001 keV能区确定铀富集度的方法研究

在核保障领域，铀富集度是一项重要核查指标。本文提出了一种通过分析²³⁵U、²³⁸U和²²⁸Th （²³²U的衰变子体）的特征γ能峰拟合相对探测效率曲线确定铀富集度的方法，编写了铀富集度分析程序。用HPGe探测器对两种化学形态、富集度范围为1.8%~90.2%的铀样品进行了重复性测量。结果显示，富集度的测量分析值与标称值的相对偏差小于3%。     

Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors

This paper is aimed at the development of a fuel cycle concept for host countries with a lack of nuclear infrastructure. To minimize plutonium proliferation concern the adoption of long-life core with no fuel radiochemical treatment on site is suggested. Current investigation relies upon light water reactor technology and plutonium-free fresh fuel. Erbium doped to uranium oxide (enrichment 19.8%) fuel is selected as the reference. Such a high enrichment is selected in attempt to approach the longest irradiation time in one batch mode. In addition to that, uranium enriched up to 20% does not consider as a nuclear material for direct use in weapon manufacture. A sequence of two irradiation cycles for the same fuel rods in two different light water reactors is the key feature of the advocated approach. It is found that the synergism of PWR and pressure tube graphite reactor offers fuel burnup up to 140GWd/tHM without compromising safety characteristics. Being as large as 8% in the final isotopic vector, fraction of ²³⁸Pu serves as an inherent protective measure against plutonium proliferation.     

Computation on Fuel Particle Size Capable of Being Regarded as Homogeneous in Nuclear Criticality Safety Analysis

For powdered fuel processed in the nuclear fuel facilities, flooding is often thought to be the severest condition regarding the nuclear criticality safety evaluation. The reactivity of such a heterogeneous system as powdered fuel in water should be almost equal to that of the homogeneous one, when the fuel particle size is very small. The neutron multiplication factor was calculated for an infinite cubic array of slightly enriched UO₂ sphere particles immersed in water with various enrichments, water to fuel ratios and fuel particle sizes. The calculations were performed with a computer code module based on the collision probability method to solve the ultra-fine energy group equations of neutrons. The change in the neutron multiplication factor from the homogeneous system is dominated first by the change in the resonance escape probability and second by the change in the thermal utilization factor; these changes and therefore their sum, depend almost completely on the mean uranium concentration (or water to fuel volume ratio) and rarely on uranium enrichment up to 10 wt% for a fuel particle size of 1mm. The dependence determines the fuel particle size regarded as homogeneous in proportion to the negligible relative error of the neutron multiplication factors.     

我国核燃料循环前端产业的现状和展望

在分析我国核燃料循环产业面临发展机遇的基础上,阐述了天然铀的保障供给、铀转化和铀浓缩、燃料制造领域等核燃料循环产业的现状以及面临的挑战,并对我国核燃料循环前端产业的发展方向进行了分析预测,针对如何应对挑战提出了相应的对策。     

γ能谱法在快堆新燃料235U富集度核实测量中的应用

对快堆新燃料组件铀富集度进行了非破坏性核实测量,γ能谱法是测量铀富集度首选方法之一,快堆新燃料235U富集度真实值为64.4％【1】,235U富集度越高测量分析需要时间相对越长,本次核实测量工作量大,环境本底高,精确测量十分困难,对系统硬件的要求很高,能谱解析和数据处理过程更复杂。本次对多根燃料单棒实施了γ能谱法测量,利用专业的软件分析得到235U富集度与真实值绝大部分偏差在3%以内。     

我国核燃料循环前端产业的现状和展望

在分析我国核燃料循环产业面临发展机遇的基础上,阐述了天然铀的保障供给、铀转化和铀浓缩、燃料制造领域等核燃料循环产业的现状以及面临的挑战,并对我国核燃料循环前端产业的发展方向进行了分析预测,针对如何应对挑战提出了相应的对策。     

Denaturing of highly enriched uranium with U: Protection against uncontrolled proliferation

The paper is addressed to the problem how to impart nuclear materials the properties of inherent protective barriers, which are able to impede substantially or even make it practically impossible to extract and use highly enriched uranium fuel for non-energy production purposes. It is demonstrated that highly enriched uranium, doped with 1% ²³²U, acquires inherent proliferation resistance, at least, at the level of uranium enriched up to 20% ²³⁵U. This property is well supplemented with previous results (Shmelev, A.N., Kulikov, G.G., 1997. About neutron-physical features of the modified (denatured) fuel cycles. Communications of Higher Schools, Nuclear Power Engineering, No. 6, pp. 42–48.) demonstrating improvement of neutron-multiplying properties in such a fuel. Another important circumstance consists in the fact that application of uranium enrichment technologies for so denatured uranium fuel is substantially hampered.