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EVALUATION OF A POTASSIUM FILLED UO_2 CORE IN A BERYLLIUM-REFLECTED SPACE REACTOR

机译:铍反射空间反应器中钾填充UO_2核的评价

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The critical configuration of the small, compact critical assembly (SCCA) experiments performed at the Oak Ridge Critical Experiments Facility (ORCEF) in 1962-1965 have been evaluated for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and were determined to be acceptable benchmark experiments and are included in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook). The initial intent of these experiments was to support the design of the Medium Power Reactor Experiment (MPRE) program, whose purpose was to study "power plants for the production of electrical power in space vehicles." The third configuration in this series of experiments was a beryllium-reflected mockup of a stainless-steel-clad, highly enriched uranium (HEU)-O_2 fuel, potassium-cooled, space power reactor. Reactivity measurements, cadmium ratio spectral measurements, and fission rate measurements were measured through the core and top reflector. Fuel effect worth measurements and neutron moderating and absorbing material worths were also measured in the assembly fuel region. The cadmium ratios, fission rate, and worth measurements were evaluated for the International Reactor Physics Experiment Evaluation Project (IRPhEP) and are published in the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook). More recently, two additional critical configurations have been evaluated and added to the existing evaluation report in the ICSBEP Handbook. The new critical configurations measure the effect of filling the core with potassium. The critical configuration consisted of 30.48 cm tall fuel tubes of 93.15 wt.% enriched uranium dioxide (UO_2) pellets. Each fuel tube had 26 pellets with a total mass of 295.8 g UO_2 per tube. There were 253 tubes were arranged with 1.506-cm center-to-center, triangular spacing and surrounded on all side by a beryllium reflected. The reactivity of the system was measured with the core tank empty and filled with potassium. The system reactivity was increased from 13.4 ¢ to 32 ¢. This change in system reactivity represents the worth of the potassium. Simple benchmark models for the empty and potassium filled cores have been derived and evaluated and found to be acceptable as benchmark experiments. The benchmark experiment eigenvalues are 1.0001 ±0.0008 and 1.0011 ±0.0009 for the empty and filled cores, respectively. When calculated with MCNP5 and ENDF/B-Ⅶ.0 the calculated eigenvalues are 0.98906 ± 0.00002 and 0.98883 ± 0.00002, respectively. These results are concerning due to the drop of the calculated system reactivity when potassium is added to the system rather than the expected increase in system reactivity.
机译:1962-1965年在橡树岭关键实验设施(ORCEF)上执行的小型紧凑型关键组件(SCCA)实验的关键配置已通过国际关键安全性基准评估项目(ICSBEP)进行了评估,并确定为可接受的基准实验,并包含在《国际评估的临界安全性基准实验手册》(ICSBEP手册)中。这些实验的最初目的是支持中功率反应堆实验(MPRE)程序的设计,该程序的目的是研究“用于在航天器中生产电能的发电厂”。这一系列实验的第三个配置是铍反射的不锈钢包层高浓缩铀(HEU)-O_2燃料,钾冷却的空间动力反应堆的样机。反应性测量,镉比光谱测量和裂变速率测量是通过纤芯和顶部反射器进行的。还测量了组装燃料区域中的燃料效应价值测量值以及中子减速和吸收材料的价值。对国际反应堆物理实验评估项目(IRPhEP)评估了镉比率,裂变率和有价值的测量值,并将其发布在《国际反应堆物理基准实验手册》(IRPhEP手册)中。最近,对另外两个关键配置进行了评估,并将其添加到《 ICSBEP手册》中的现有评估报告中。新的关键配置可测量用钾填充核芯的效果。关键配置由30.48厘米高的燃料管组成,这些燃料管具有93.15 wt。%的浓缩二氧化铀(UO_2)颗粒。每个燃料管具有26个芯块,每根管的总质量为295.8 g UO_2。共有253个试管,中心到中心的间距为1.506厘米,呈三角形间隔,并在所有侧面被铍反射物包围。在核心罐为空并充满钾的情况下测量系统的反应性。系统反应性从13.4 increased增加到32 ¢。系统反应性的这种变化代表了钾的价值。已经得出并评估了用于空芯和钾芯的简单基准模型,并被认为可以作为基准实验。空芯和实芯的基准实验特征值分别为1.0001±0.0008和1.0011±0.0009。用MCNP5和ENDF / B-.0计算时,计算出的特征值分别为0.98906±0.00002和0.98883±0.00002。这些结果令人关注,因为当向系统中添加钾时,系统计算出的反应性下降,而不是系统反应性的预期增加。

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