Shogo Noda, S. Sukarman, A. Yamaji, Tetsuo Takei, T. Fukuda, Arisa Ayukawa
{"title":"不同冷却剂密度下多轴燃料换流的超级快堆堆芯设计研究","authors":"Shogo Noda, S. Sukarman, A. Yamaji, Tetsuo Takei, T. Fukuda, Arisa Ayukawa","doi":"10.1115/ICONE26-81501","DOIUrl":null,"url":null,"abstract":"The Super Fast Breeder Reactor (Super FBR) utilizes supercritical light water as coolant, which changes from liquidlike high density state to gas-like low density state continuously in the core without phase change. In the preceding study (Noda et al., 2017), new concept of axially heterogeneous core with multi-axial fuel shuffling was proposed. The core consisted of two layers of mixed oxide (MOX) fuel and two layers of blanket fuel with depleted uranium (DU), which were arranged alternatively in the axial direction. The study showed that, with independent fuel shuffling in the upper part and lower part of the core, breeding performance could be improved by increasing the upper blanket fuel batch number while keeping the fuel batch number of the rest of the core unchanged, because of increased neutron flux in the upper blanket. However, the study did not consider influence of different coolant density histories in the different axial level of the core on the core neutronics. Hence, this study aims to reveal influence of the different coolant density histories through design and analyses of the multi-axial fuel shuffling core with two MOX layers and three blanket layers. The three levels correspond to the coolant density below, around, and above the pseudo-critical temperature. The neutronics calculations are carried out with SRAC 2006 code and JENDL-3.3 nuclear data library. Unit cell burnup calculations based on collision probability method are carried out for 5 different coolant density histories to consider influence of different neutron spectrum on breeding performance of the core. Influence of instantaneous coolant density changes on the core neutronics are considered by coupling core burnup calculations with thermal-hydraulics calculations based on single channel model. Influence of independent fuel shuffling of the upper blanket on the core neutronics (breeding performance and void reactivity characteristics) is investigated, followed by a similar investigation on the lower blanket. The differences between the two schemes are investigated since coolant density histories are greatly different between the upper blanket and the lower blanket.","PeriodicalId":354697,"journal":{"name":"Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues","volume":"131 3 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2018-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":"{\"title\":\"Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density\",\"authors\":\"Shogo Noda, S. Sukarman, A. Yamaji, Tetsuo Takei, T. 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引用次数: 2
摘要
超级快中子增殖反应堆(Super FBR)利用超临界轻水作为冷却剂,在堆芯内由液态高密度状态连续变化到气态低密度状态,无相变。在之前的研究中(Noda et al., 2017),提出了轴向非均质堆芯多轴向燃料混叠的新概念。堆芯由两层混合氧化物(MOX)燃料和两层贫铀(DU)包层燃料组成,沿轴向交替排列。研究表明,在堆芯上下部分燃料独立混叠的情况下,由于堆芯上包层的中子通量增加,在增加堆芯上包层燃料批号的同时保持堆芯其余部分燃料批号不变,可以提高堆芯的增殖性能。然而,该研究没有考虑不同冷却剂密度历史在堆芯不同轴向水平对堆芯中子的影响。因此,本研究旨在通过设计和分析两层MOX和三层包层的多轴燃料混流堆芯,揭示不同冷却剂密度历史对堆芯的影响。这三个级别对应于冷却剂密度低于、接近和高于伪临界温度。利用SRAC 2006程序和JENDL-3.3核数据库进行中子计算。为考虑不同中子谱对堆芯增殖性能的影响,对5种不同的冷却剂密度历史进行了基于碰撞概率法的单体电池燃耗计算。通过将堆芯燃耗计算与基于单通道模型的热工水力学计算耦合,考虑了冷却剂密度瞬时变化对堆芯中子电子学的影响。研究了上包层的独立燃料变换对堆芯中子(增殖性能和空洞反应特性)的影响,随后对下包层进行了类似的研究。由于上包层和下包层之间的冷却剂密度历史差异很大,因此研究了两种方案之间的差异。
Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density
The Super Fast Breeder Reactor (Super FBR) utilizes supercritical light water as coolant, which changes from liquidlike high density state to gas-like low density state continuously in the core without phase change. In the preceding study (Noda et al., 2017), new concept of axially heterogeneous core with multi-axial fuel shuffling was proposed. The core consisted of two layers of mixed oxide (MOX) fuel and two layers of blanket fuel with depleted uranium (DU), which were arranged alternatively in the axial direction. The study showed that, with independent fuel shuffling in the upper part and lower part of the core, breeding performance could be improved by increasing the upper blanket fuel batch number while keeping the fuel batch number of the rest of the core unchanged, because of increased neutron flux in the upper blanket. However, the study did not consider influence of different coolant density histories in the different axial level of the core on the core neutronics. Hence, this study aims to reveal influence of the different coolant density histories through design and analyses of the multi-axial fuel shuffling core with two MOX layers and three blanket layers. The three levels correspond to the coolant density below, around, and above the pseudo-critical temperature. The neutronics calculations are carried out with SRAC 2006 code and JENDL-3.3 nuclear data library. Unit cell burnup calculations based on collision probability method are carried out for 5 different coolant density histories to consider influence of different neutron spectrum on breeding performance of the core. Influence of instantaneous coolant density changes on the core neutronics are considered by coupling core burnup calculations with thermal-hydraulics calculations based on single channel model. Influence of independent fuel shuffling of the upper blanket on the core neutronics (breeding performance and void reactivity characteristics) is investigated, followed by a similar investigation on the lower blanket. The differences between the two schemes are investigated since coolant density histories are greatly different between the upper blanket and the lower blanket.