铀溶液核临界安全实验装置

硝酸铀溶液液核临界安全实验装置专门用于研究乏燃料后处理中储存容器的核临界安全问题。为了得到我国自己的核临界安全实验数据，中国原子能科学研究院设计，建造了铀溶液核临界安全实验装置，实验装置的活性区硝酸铀酰溶液内可含中子吸收体或不含中子吸收体，活性区可有反射层或没有反射层，在以上四种条件下，可对不同硝酸铀酰溶液浓度进行临界试验研究，该实验装置具有多种安全保护措施，但运行方式简便，启动，停止容易，单次误操作不危及实验装置的特点，该装置还具有可视性定量，限量自动加料系统，高精度全程液位测量计以及采用多操作步骤才能完成‘一次注量’的控制方式等特点，安全分析认为该装置造成核临界事故的概率为10^-8。     

临界实验装置水位外推达临界方法优化研究

带乏燃料的临界实验装置可用于开展乏燃料贮存相关的临界实验研究,考虑到其具有较高放射性,因此开展实验时最佳方法是水位外推达临界方法。目前该带乏燃料的临界实验装置尚未建成,遂使用与其堆芯结构、物理特性相似的铀棒栅轻水慢化临界实验装置开展水位外推达临界方法的模拟实验。在该实验中,由于水的屏蔽作用随水位上升不断加深导致无法得到正常的外推曲线。本文通过蒙特卡罗程序模拟外推过程,研究了中子源与探测器在不同的相对位置处中子计数率随水位变化的规律,给出了探测器与中子源的优化布置方案。此外,还提出一种以水位价值作为外推参数的外推方法,消除了水位高度外推时水位系数不均匀的影响,使得外推结果更准确。     

铀溶液核临界安全实验装置控制保护系统

主要阐述了铀溶液核临界安全实验装置控制保护系统的设计思想、保障技术和系统原理。     

铀溶液临界实验装置温度效应计算研究

临界安全在反应堆物理中是一非常重要的课题，而溶液系统的临界安全是其中的一个方面。本工作以目前国内唯一的铀溶液临界实验装置为例，对其温度效应进行研究，计算了该装置的温度系数，为装置的下一步改造提供了一定的理论支持。     

控制棒价值对外推临界试验的影响分析

针对外推临界试验中应用控制棒价值的效果进行研究。在零功率反应堆上进行外推临界试验,基于外推临界试验中子计数,采用考虑和未考虑控制棒价值的外推方法进行分析。结果表明:在前几步外推临界过程,控制棒价值对外推临界棒位的影响较为明显,对指导外推提棒存在一定影响,未考虑控制棒价值的外推1/2添加棒位会出现超过临界棒位的情况;在外推临界过程中,考虑控制棒价值的外推方法更加准确,所得外推结果更加安全。     

临界外推中对控制棒价值非线性的修正

研究堆在物理启动时一般通过棒位外推法得出临界棒位,从而逐步达到临界。但由于控制棒积分价值的非线性,使得这一外推过程不安全或过于偏保守,特别是当临界棒位处于非线性区时。根据点堆模型可导出计数率倒数与Δk_eff成正比,若根据积分价值曲线将棒位对应为Δk_eff,则可修正控制棒价值非线性的影响。通过研究堆的临界外推数据验证了这一方法的准确性。     

启明星1#快热交界面能谱变化对外推临界实验结果影响分析

加速器驱动的次临界系统（ADS）基准装置启明星1#在外推临界实验过程中,快热交界面探测器计数率与其他位置探测器计数率存在较大异常。本工作对该实验装置外推临界实验开展数值模拟,并对快热交界面的中子能谱进行详细计算,根据计算结果对探测器在外推临界实验中的计数率异常现象进行分析。结果表明,快热交界面能谱随燃料装载量的变化是引起探测器计数率异常的主要因素,这为今后快热耦合次临界实验装置开展中子学实验研究提供了理论依据。     

噪声法测量临界装置温度系数实验研究

为了用噪声法测量核电站反应堆的负慢化剂反应性温度系数(MTC),本文在铀溶液临界装置上研究噪声法实验测量反应性温度系数αT,并与周期法测量的αT进行比较。结果表明,两种方法测量的αT趋势基本一致。由于铀溶液临界装置中溶液的反应性温度效应与核电站反应堆的慢化剂温度效应的机理相似,因此本文利用噪声法测量铀溶液临界装置的αT对于核电站反应堆利用噪声法测量MTC有一定的参考价值。     

启动物理实验中PNS的堆外探测器响应和外推临界研究

使用MCNP5对启动物理实验中一次中子源(PNS)在堆外源量程探测器(SRD)响应进行模拟计算,分析堆芯有效倍增因子effk、带源有效倍增因子sk和探测器计数C之间的关系。通过对SRD响应系数a的预测,得到优于传统的1/C外推预测临界法的a'/C外推预测临界法,使硼稀释过程中的外推曲线线性度更好。计算结果表明,接近临界时a'/C值与eff1?k线更加吻合。     

铀棒栅临界实验装置水堆安全棒系统结构设计及实验验证

为满足核安全法规的要求和铀棒栅临界实验装置水堆紧急停堆的需要,设计了8根镉棒并排组成的安全棒,采用电磁铁断电以实现快速下落,达到紧急停堆的目的。经实验验证,该系统性能稳定可靠、重复性好,安全棒价值为1.125×10^-2 Δk/k,快速下落时间为(0.363±0.002) s,满足核安全法规的要求,为铀棒栅临界实验装置水堆的安全运行提供了保障。     

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.     

Criticality configuration design methodology applied to the design of fuel debris experiment in the new STACY

ABSTRACT

The new critical assembly STACY will be able to contribute to the validation of criticality calculations related to the fuel debris. The experimental core designs are in progress in the frame of JAEA/IRSN collaboration. This paper presents the method applied to optimize the design of the new STACY core to measure the criticality characteristics of pseudo fuel debris that simulated Molten Core Concrete Interaction (MCCI) of the fuel debris. To ensure that a core configuration is relevant for code validation, it is important to evaluate the reactivity worth of the main isotopes of interest and their k_eff sensitivity to their cross sections. In the case of the fuel debris described in this study, especially for the concrete composition, silicon is the nucleus with the highest k_eff sensitivity to the cross section. For this purpose, some parameters of the core configuration, were adjusted using optimization algorithm to find efficiently the optimal core configurations to obtain high sensitivity of silicon capture cross section. Based on these results, realistic series of experiments for fuel debris in the new STACY could be defined to obtain an interesting feedback for the MCCI. This methodology is useful to design other experimental conditions of the new STACY.