能量到GeV的质子入射铅靶的散裂产物分布研究(英文)

由中高能质子入射靶引起的散裂碎片的分布关系到散裂靶经长期辐照后的放射性废物的累积。在量子分子动力学模型(QMD)中考虑剩余核的裂变过程(FISSION),利用QMD FISSION模型研究了322,660,759 MeV的质子入射铅靶的散裂产物的分布。计算结果很好地再现了实验测量值。     

Prediction of minimum UO2 particle size based on thermal stress initiated fracture model

An analytic study was employed to determine the minimum UO₂ particle size that could survive fragmentation induced by thermal stresses in a UO₂---Na fuel-coolant interaction (FCI), based on a brittle fracture mechanics approach. Solid and liquid UO₂ droplets were considered, with perfect wetting by the sodium or finite heat transfer coefficient. The analysis indicated that particles below the range of 50 μm in radius could survive an FCI under the most severe temperature conditions without thermal stress fragmentation, and seemed to verify the experimental observations as to the range of the minimum particle size due to thermal stress fragmentation by FCI. The basic complexities in fracture mechanics make further investigation in this area interesting but not necessarily fruitful for the immediate future.     

基于WIMS-D库燃耗数据的更新与基准验证

随着AP1000等新一代压水堆的发展,燃耗深度在不断提高,平均卸料燃耗深度提高到60 GW d·t-1。然而,传统使用的WIMS69群和XMAS172群WIMS-D格式多群常数库,其能群结构存在共振峰重叠,核素种类较少,裂变产物产额的偏差较大,并且伪裂变产物中包含的核素种类较多而导致152Gd、160Gd、159Tb、160Tb等重要核素无法得到精确处理等问题。因此,本文主要针对AP1000等新一代反应堆的设计以及运行特点,基于ENDF/B-VII.1库,并且在现有基础上针对WIMS-D库中的伪裂变产物、裂变产物燃耗链以及裂变产物产额等燃耗数据进行更新,再通过NJOY程序开发了SHEM281群WIMS-D格式多群常数库。通过DRAGON程序挂载该WIMSD281库,对其进行临界和燃耗两方面基准验证。计算结果表明,该数据库的计算结果与基准值符合较好,精度较高,结果可靠,可初步用于压水堆的相关计算。     

Nondestructive burnup measurements by gamma-ray spectroscopy on spent fuel elements of the RP-10 research reactor

Gamma-ray spectroscopy is an important nondestructive method for the qualification of irradiated nuclear fuels. Regarding research reactors, the main parameter required in the scope of such qualification is the average burnup of spent fuel elements. This work describes the measurement, using nondestructive gamma-ray spectroscopy, of the average burnup attained by Material Testing Reactor (MTR) fuel elements irradiated in the RP-10 research reactor. Measurements were performed at the reactor storage pool area using ¹³⁷Cs as the only burnup monitor, even for spent fuel elements with cooling times much shorter than two years. The experimental apparatus was previously calibrated in efficiency to obtain absolute average burnup values, which were compared against corresponding ones furnished by reactor physics calculations. The mean deviation between both values amounts to 6%.     

Fundamental burn-up mode in a pebble-bed type reactor

This paper deals with a pebble-bed type reactor, in which the fuel is loaded from one side (top) and discharged from the other side (bottom). A boundary value problem of a single group diffusion equation coupled with simplified burn-up equations is studied, where the natural radioactive decay processes are neglected in the burn-up modelling. An asymptotic burning wave solution is found analytically in the one-dimensional case, which is called as fundamental burn-up mode. Among this solution family there are two particular cases, namely, a classic fundamental solution with a zero burn-up and a partial solitary burn-up wave solution with a highest burn-up. An example of Th–U conversion is considered and the solutions are presented in order to show the mechanism of the burning wave.     

First-principles study on the diffusion behavior of Cs and I in Cr coating

Cs and I can migrate through fuel-cladding interfaces and accelerate the cladding corrosion process induced by the fuel-cladding chemical interaction.Cr coating has emerged as an important candidate for mitigating this chemical interaction.In this study,first-principles calculations were employed to investigate the diffusion behavior of Cs and I in the Cr bulk and grain boundaries to reveal the microscopic interaction mitigation mechanisms at the fuel-cladding interface.The interaction between these two fission products and the Cr coating were studied systematically,and the Cs and I temperature-dependent diffusion coefficients in Cr were obtained using Bocquet's oversized solute-atom model and Le Claire's nine-frequency model,respectively.The results showed that the Cs and I migration barriers were significantly lower than that of Cr,and the Cs and I diffusion coefficients were more than three orders of magnitude larger than the Cr self-diffusion coefficient within the temperature range of Generation-Ⅳ fast reactors(below 1000 K),demonstrating the strong penetration ability of Cs and I.Furthermore,Cs and I are more likely to diffuse along the grain boundary because of the generally low migration barriers,indicating that the grain boundary serves as a fast diffusion channel for Cs and I.     

A model study of displacement cascades distributions in zirconium

5 to 200 keV displacement cascades in zirconium are studied in the binary collision approximation with the simulation code Marlowe. The cascades are analysed statistically by means of component analysis, fuzzy clustering and isodata analysis. As a consequence of the large recoil ranges and range straggling specific to open hcp lattices like Zr, a large dispersion of the frequencies of Frenkel pair distributions is found, as well as of the spatial extent and morphology of vacancy and interstitial distributions. In Zr, cascades are formed by a widespread distribution of displacement clusters that can be small. Remarkably, the size and morphology distributions of these clusters are found independent of the primary recoil energy in the energy range investigated.     

Opacity calculation based on average atom model

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新型复合无机离子交换剂磷酸钛-AMP回收~(137)Cs的研究

本文叙述了新型复合无机离子交换剂磷酸钛-AMP的制备及其从模拟的1AW中回收~(137)Cs的性能。研究了不同酸度和Na/Cs比对~(137)Cs交换容量的影响,再生循环及γ源辐照对~(137)Cs交换容量的影响;Na、Rb、Sr、Ce等沾污核素去污因数的测定。简介了以冷却两年的混合裂片为指示剂、从模拟的1AW中回收~(137)Cs及用γ能谱和纸层析法对产品中杂质含量的测定。结果表明,这种复合交换剂对Cs具有相当高的选择交换容量、良好的化学稳定性和辐照稳定性、并提出了相应的工艺流程。     

AP1000核电站~(106)Ru正常运行源项研究

AP1000核电站一回路中~(106)Ru的现实源项远远高于其设计源项,其一回路活度浓度与131I相当,既从理论计算分析不可信,又与电厂实际测量数据不符。一回路~(106)Ru活度浓度过高,使得电厂液态流出物中106Ru及其子体~(106)Rh占到除氚和碳-14外放射性年排放量预期值的一半以上,严重背离电厂运行经验,而且对AP1000电厂流出物监测、环境监测和环境影响评价造成了误导。本文分析了ANSI/ANS-18.1中现实源项计算方法存在的问题,研究提出了从一回路主要核素活度浓度出发计算~(106)Ru现实源项的方法,其计算结果与M310/CPR1000、VVER-1000等国内压水堆电厂的现实源项基本一致,能客观反映压水堆电厂~(106)Ru源项,可供国内AP1000核电厂源项计算时参考。     

基于多元线性回归模型的中性束质子比分析

中性束质子比的高低对其注入等离子体后的加热效果具有重要的影响。实验中,强流离子源的灯丝电压、弧压、进气量等宏观运行参数决定了中性束质子比的大小。以东方超环中性束注入测试台束引出实验为基础,利用多元线性回归模型对引出中性束质子比进行分析,建立了影响中性束质子比的预测方程,并对该模型的正确性进行了检验。结果表明,中性束质子比可利用以灯丝电压和弧压为自变量的多元线性回归模型进行分析,灯丝电压是影响质子比的关键参数,弧压次之。     

无侵蚀非农耕地土壤137Cs深度分布入渗过程模型

在阐明土壤中137Cs扩散与迁移过程的基础上,建立了无侵蚀非农耕地土壤137Cs深度分布入渗过程模型,再现了重庆开县和陕北子长两个剖面137Cs深度分布的变化过程.重庆开县剖面137Cs深度分布(2004年)为指数衰减形态,表层土壤137Cs浓度最高,137Cs深度分布形态系数ho=0.0997 cm-1,入渗系数D=0.8006cm2·a-1.陕北子长剖面137Cs深度分布(2001年)为非指数衰减形态,次表层土壤浓度最高,全剖面拟合的深度分布形态系数ho=0.0825 cm-1,入渗系数D=1.24 cm2·a-1.子长剖面137Cs深度分布为非指数衰减形态的原因主要是表层和次表层土壤随深度增加土壤孔隙度或水分入渗速率急剧降低,导致137Cs入渗速率随深度增加而降低,137Cs入渗系数(D)为负值.     

基于概率因果模型与遗传算法的船舶核动力装置故障诊断的新方法

介绍一种将概率因果模型和遗传算法相结合的核动力装置二回路凝给水系统的故障诊断方法,它将概率因果模型的似然函数作为遗传算法的适应函数,从而将复杂系统的故障诊断转化为最优问题。仿真结果表明,该方法能够适应诊断过程中出现的不确定性,并实现多故障诊断,具有较高的诊断可靠性和实用性。     

基于WEB的BES数据存储系统模型

讨论了基于WEB的数据存储系统模型的系统结构和基本方法。从BES数据结构分析、数据处理过程、系统结构设计、实验方案选择、关键技术以及图像处理等方面详细介绍了系统模型的实现过程,守成了从系统实验软硬件平台的建立到数据装入、数据库建立、数据存取、数据远程处理以及数据图形处理等功能。     

基于多元统计技术的铀矿蚀变信息高光谱模型

介绍了一种基于数理统计分析技术的铀矿蚀变信息高光谱建模技术,它利用了高光谱数据细微、丰富的光谱信息,根据岩石和蚀变的光谱特征与物质成分的关系,通过矿物中特定离子或离子基团的诊断性吸收谷的特征参数反演岩矿的物质成分,从而综合识别蚀变信息,将为航空和航天成像光谱遥感的应用开辟一个矿物蚀变信息识别和区分的研究途径。     

基于蒙特卡罗方法的三维燃耗计算研究

采用通过编写连接MCNP程序和ORIGEN2程序的接口处理程序的方法进行快中子系统的燃耗计算。由MCNP、ORIGEN2、接口处理程序和截面文件组成的软件系统可用于燃料或堆芯非均匀布置快中子系统的燃料同位素成分和燃耗反应性损失计算,在燃耗反应性损失计算中采用了伪裂变产物的方法。介绍程序系统的研制情况,并给出用该软件系统计算中国实验快堆首炉堆芯和OECD/NEAMOX燃料快堆基准题的燃耗计算结果。     

Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model

To investigate the steady thermal hydraulic characteristics of U-tube steam generator(SG), a 1D simulation code based on the four-equation drift flux model is developed. The U-tube channels presumably consist mainly of the primary channel, secondary channel, and tube wall. In the sub-cooling regions of the primary and secondary channels, flow is simulated using the single-phase flow model, whereas that in the boiling regions of the secondary channels is simulated using the four-equation drift flux model. The first-order equations of upwind difference are derived based on the staggered grid. Steady-state thermal hydraulic parameters are obtained with a cross-iteration scheme of heat balance and natural circulation requirement. The developed code is applied to analyze the SG behavior of the Qinshan I Nuclear Power Plant under 100%, 75%, 50%, 30%, and 15% power conditions. Analysis results are then compared with the simulation results obtained using RELAP5.     

用于便携式X射线荧光仪的基体效应散射校正模型

本文论证了样品对入射射线的质量吸收系数(μ_O)与康普顿散射强度之倒数呈线性关系,提出并验证了样品对待测元素特征线的质量吸收系数(μ_K)与质量吸收系数(μ_O)以及待测元素含量之间呈线性多项式关系。并且给出了这些关系存在的条件。提出了一种适用于低能量分辨率的携带式X荧光仪的散射校正模型。并成功用于锡矿和某些铜矿分析中。