小型长寿命压水堆燃料电池中UO2和(Th,U-233)O2性能的比较研究

Mardiana Napirah, Z. Su’ud
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引用次数: 0

摘要

对小型长寿命压水堆中UO2和(Th,U-233)O2燃料的性能进行了比较研究。利用SRAC2006的PIJ模块对一个运行10年的燃料电池进行了中子计算。通过改变UO2中U-235和(Th,U-233)O2中U-233的富集度1%-20%以及改变燃料体积分数40%、45%、50%、55%和60%来进行计算。通过比较每种燃料类型在10年内获得临界所需的浓缩度、无限增殖因子(k-inf)值和转化率(CR)值来观察性能。计算结果表明,对于两种燃料类型,60%的燃料体积分数给出了无限增殖因子最低、转化率最高的临界条件。而就所需的裂变核素富集而言,(Th,U-233)O2比UO2具有更好的性能,因为(Th、U-233)氧气中只需要5%的U-233,而UO2需要9%的U-235才能在10年的运行中达到临界。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Comparative Study of UO2 and (Th,U-233)O2 Performance in Small Long-Life PWR Fuel Cell
A study was performed comparing the performance of UO2 and (Th,U-233)O2 fuel in small long-life PWR. The neutronic calculation carried out by PIJ module of SRAC2006 was done to a fuel cell in 10 years of operation. The calculation was conducted by varying the enrichment of U-235 in UO2 and U-233 in (Th,U-233)O2 for 1% - 20% and also by varying the fuel volume fraction for 40%, 45%, 50%, 55%, and 60%. The performance was observed by comparing the enrichment needed by each fuel type to gain criticality in 10 years, the infinite multiplication factor (k-inf) value, and the conversion ratio (CR) value. The calculation results showed that 60% fuel volume fraction gave critical conditions with the lowest infinite multiplication factor and highest conversion ratio for both fuel types. While in terms of fissile nuclide enrichment needed, (Th,U-233)O2 had better performance than UO2, because only 5% U-233 was needed in (Th,U-233)O2 while UO2 needed 9% U-235 to gain criticality in 10 years of operation.
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