Neutronic and nonproliferation characteristics of (PuO2-UO2) and (PuO2-ThO2) as fast reactor fuels
Neutronic and nonproliferation characteristics of (PuO2-UO2) and (PuO2-ThO2) as fast reactor fuels
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DOI：
10.1016/j.nucengdes.2009.05.019
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发表时间：
2009-10-01
影响因子：
1.7
通讯作者：
Nelson, Paul
中科院分区：
文献类型：
--
作者：
Chirayath, Sunil Sunny;Hollenbeck, Gordon;Nelson, Paul
计算堆芯物理分析进行了一个典型的快中子增殖反应堆（FBR）的核心设计，通过两个案例研究，一个只使用（PuO 2-UO 2）混合氧化物燃料和另一个取代类似的41%（PuO 2-UO 2）混合氧化物与（PuO 2-ThO 2）混合氧化物，同时保存总钚含量。所采用的基本计算框架使用MONTEBURNS 2 PERL脚本来耦合中子代码MCNP 5与耗尽/燃耗代码ORIGEN 2.2。计算和比较的参数是：净中子增殖因子（k（eff））;区域平均中子能谱：中子通量;热功率分布：增殖比;燃料燃耗;裂变材料积累/贫化-U-232积累;与燃料温度相关的多普勒效应、与冷却剂温度相关的钠膨胀系数以及剂量率、自发裂变和伽马辐射等防扩散特性。案例研究的分析表明，核心的物理特性，除了k（eff），只有轻微的不同，在两种情况下，如果不相等的幅度。第一个案例研究表明，从平衡堆芯排出的8个径向包层子组件（武器级钚）或1个乏燃料子组件（反应堆级钚）的转移足以获得大量（SQ）。第二个案例研究表明，在快堆的所有燃料分组件中，通过外围装载（PuO 2-ThO 2）MOX针，可以大大提高防扩散能力，这应有助于核材料保障。两种情况下的超铀（TRU）生成的比较表明，对于新提出的部分负载ThO 2-PuO 2的FBR设计，镎的产生减少了约60%，而其他更高的TRU，如镅，铥等，没有显示出显着的减少。(C)2009 Elsevier B. V.保留所有权利。
Computational core physics analysis carried out for a typical fast breeder reactor (FBR) core design is presented through two case studies; one using only (PuO2-UO2) MOX fuel and another that replaces similar to 41% of (PuO2-UO2) MOX with (PuO2-ThO2) MOX while conserving the total Pu content. The basic computational framework employed uses the MONTEBURNS2 PERL script to couple the neutronic code, MCNP5 with the depletion/burn-up code, ORIGEN2.2. The parameters computed and compared are: net neutron multiplication factor (k(eff)); regionally averaged neutron spectrum: neutron flux; thermal power distribution: breeding ratio; fuel burn-up; fissile material build-up/depletion-U-232 build-up; and fuel temperature dependent Doppler Effect, coolant temperature dependent sodium expansion coefficient, and nonproliferation characteristics such as dose rates, spontaneous fission and gamma emissions. The analyses of the case studies indicate that the core physics characteristics, except k(eff), are only marginally different in their magnitudes between the two cases, if not equal. The first case study shows that diversion of either 8 radial blanket sub-assemblies (weapon grade Pu) or 1 spent fuel sub-assembly (reactor grade Pu) discharged from an equilibrium core is sufficient to derive a significant quantity (SQ). The second case study shows that a considerable improvement in proliferation resistance can be achieved with the peripheral loading of (PuO2-ThO2) MOX pins in all the fuel sub-assemblies of a fast reactor, which should aid in nuclear material safeguards. The comparison of transuranic (TRU) generation for both the cases showed that about 60% reduction in neptunium production has been achieved for the new proposed partially ThO2-PuO2 loaded FBR design, whereas other higher TRUs like americium, curium, etc. did not show significant reduction. (C) 2009 Elsevier B.V. All rights reserved.