Analysis Loading Height of HTR (High Temperature Reactor) Core to Obtain Criticlity of Reactor

E. Setiawati
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引用次数: 3

Abstract

High temperatur reactor (HTR) attract to be studied due to it has inherent safety characteristics and capabilities to produce energy economically. Design of reactor core in this study is a blend HTR 10 in China with HTR pebble-bed. The reactor has thermal power of 10 MW with inlet and outlet helium temperatures of 250 o C and 700 o C. HTR design is a cylindrical with helium gas as a coolant and graphite as a moderator. The HTR uses pebble-bed fuel composed a large amount of particles of TRISO in graphite metrics. Kernel radius used to analyse reactor core height in this research is 225 µm with enrichment of 16% in order to achieve critical condition. Reactor criticality is also influenced by the height of active reactor core where pebble-bed fuel is distributed. Calculation of the reactor criticality at any height variations active core is done with MCNP5 modelling techniques. The modelling is done by making the geometry of reactor and pebble-bed which is distributed by using body-centred cubic lattice in the reactor core. From the MCNP5 calculation, the first criticality of HTR can be achieved on the active core height of 150.9012 cm calculated from the bottom active core with criticality value of 1.00312±0.00090. The higher active reactor core is, the more increasing the reactor criticality is. This is occured due to there are many fuel balls of pebble-bed used, so that activity of fission in reactor increases. However, reactor criticality is still in stable condition in each the rise of active core height from critical core height even though reactor reactivity increases 0.01 Δk/k. The minimum of fuel needed to achieve initial criticality (critical core height) is 11,805 pebbles and 8,906 moderators.
分析高温堆堆芯的载荷高度以获得堆的临界
高温堆以其固有的安全特性和经济发电能力吸引着人们的研究。本研究的堆芯设计为国产HTR 10与HTR球床混合堆芯。该反应堆的热功率为10兆瓦,进口和出口氦气温度分别为250℃和700℃,HTR设计为圆柱形,氦气作为冷却剂,石墨作为慢化剂。高温气冷堆使用的是由石墨中大量三氧化二硫颗粒组成的球床燃料。本研究中用于分析堆芯高度的核半径为225µm,浓缩16%,以达到临界条件。堆芯的高度也会影响反应堆的临界状态。利用MCNP5模型技术计算活性堆芯在任何高度变化下的反应堆临界。通过对反应堆和球床的几何形状进行建模,球床在反应堆堆芯中采用体心立方晶格分布。根据MCNP5计算,HTR的第一个临界值为1.00312±0.00090,可在离底部活动岩心计算的活动岩心高度150.9012 cm处达到。反应堆堆芯活性越高,反应堆临界度越高。这是由于使用了许多球床燃料球,使反应堆内的裂变活动增加。然而,当活性堆芯高度比临界堆芯高度每升高0.01 Δk/k时,反应堆的临界状态仍处于稳定状态。达到初始临界(临界堆芯高度)所需的最小燃料是11,805个小卵石和8,906个慢化剂。
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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