Geometry Survey on the Convex Shaped Core for Recriticality Prevention Against CDA in Sodium-Cooled Fast Reactor

K. Chitose, Y. Tachi, T. Wakabayashi, N. Takaki
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Abstract

In sodium-cooled fast reactors, the core is not arranged in its most reactive configuration. In this case, when the fuel melts to form a molten pool, the recriticality may occur by positive reactivity insertion due to core compaction. To prevent such recriticality, special devices of the fuel subassembly structure for discharging the molten fuel from the core region, have been investigated by the Japan Atomic Energy Agency (JAEA). On the other hand, the inherent feature of core geometry and the neutron characteristics may provide the similar effect to prevent such recriticality. The purpose of this study is to design the core specification its deformation in CDA causes negative feedback to subcritical condition, without any fuel discharge device. The convex shaped core has the longer fuel length in the inner-core region and the shorter fuel in the outer-core region. Therefore, the core geometry as intact status has a lower neutron leakage effect. When the fuel melts in CDA, the core height is compacted and negative reactivity insertion is expected during molten pool formation. The convex shaped core is based on the large-scale cylindrical homogeneous core (3,600 MWth, 4.95m in core diameter, and 0.75m in core height). The calculation showed that the compaction of cylindrical core leads to a reactivity gain, whereas the convex shaped core results in negative reactivity effect. In this geometry, both inner-core and outer-core are divided into two regions. Furthermore, we introduced the smaller diameter pin for inner-core and keep uniform Pu enrichment for all regions. The smaller diameter pins in high importance region are effective for flat-distribution. Through pin diameter survey, we confirmed the advantages of smaller diameter pin, such as reducing pressure loss of core coolant and decreasing the height of molten pool.
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钠冷快堆防CDA凸型堆芯的几何研究
在钠冷却的快堆中,堆芯并没有被安排在最活跃的位置。在这种情况下,当燃料熔化形成熔池时,由于堆芯压实导致的正反应性插入可能发生临界。为了防止这种重临界,日本原子能机构(JAEA)已经研究了用于从核心区域排出熔融燃料的燃料组件结构的特殊装置。另一方面,堆芯几何形状的固有特征和中子特性也可能起到类似的防止重临界的作用。本研究的目的是设计芯型规格,其在CDA中的变形对亚临界状态产生负反馈,没有任何燃料排放装置。凸形堆芯的内堆芯区燃料长度较长,外堆芯区燃料长度较短。因此,岩心几何形态完好状态下的中子泄漏效应较低。当燃料在CDA中熔化时,堆芯高度被压实,在熔池形成过程中预期会出现负反应性插入。凸形铁心是在大型圆柱均质铁心(3600 mth,铁心直径4.95m,铁心高0.75m)的基础上设计的。计算结果表明,圆柱形铁芯的压实会使反应性增加,而凸形铁芯则会产生负反应性效应。在这种几何结构中,内核和内核都被划分为两个区域。此外,我们还引入了内芯直径较小的引脚,并在所有区域保持均匀的Pu富集。在高重要区域,较小直径的销脚对平面分布有效。通过销径测量,确定了销径较小的优点,可以减少堆芯冷却剂的压力损失,降低熔池高度。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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