CANDU反应器中含ads富集的ThO2和废UO2燃料的可再利用性分析

IF 0.9 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI:10.2298/ntrp2204289d
Busra Durmaz, Gizem Bakir, Bugra Arslan, H. Yapici
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引用次数: 0

摘要

本研究分析了在两种不同的ADS反应堆中以微量锕系元素为燃料富集的ThO2和废UO2燃料的可重复使用性。从压水堆和CANDU的乏燃料中取出乏UO2燃料。在此分析中,考虑了总裂变热功率为2156兆瓦的CANDU-37反应堆,并通过在该反应堆中燃烧分析了从先前浓缩过程中提取的14种不同浓缩燃料。利用MCNP 2.7程序进行了三维和随时间变化的临界燃烧计算。为了确定每个病例的有效燃烧时间,执行这些计算,直到kinf值降低到所有调查病例的临界阈值1.05左右。在所有浓缩燃料中,239Pu和233U可裂变同位素的年龄百分比似乎分别低于武器级钚和铀。在有效燃烧时间结束时,燃耗值可达到26.770 ~ 33.540 GWd/MTU,平均为使用NatUO2燃料的CANDU-37反应堆燃耗值的3.5 ~ 4.5倍。本研究结果表明,在能源生产方面,使用ADS设计中富集的ThO2和废UO2燃料的CANDU-37反应堆比传统CANDU-37反应堆具有更高的中子性能。
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Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor
The study presents the analysis of the reusability of ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. The spent UO2 fuels are taken out from pressurized water reactor and CANDU spent fuels. For this analysis, the CANDU-37 reactor having a total fission thermal power of 2156 MW is considered and 14 different cases of enriched fuels taken from the previous enrichment processes are analysed by burning in this reactor. The 3-D and time-dependent critical burn up calculations are carried out by using the MCNP 2.7 code. To determine the effective burn time of each case, these calculations are performed until the values of kinf decrease to about the criticality thresh old of 1.05 for all investigated cases. The percent ages of the 239Pu and 233U fissile isotopes appear to be below weapons-grade plutonium and uranium, respectively, in all enriched fuel cases. At the end of effective burn times, the burnup values can reach the values varying in the range of 26.770 and 33.540 GWd/MTU which are a mean of 3.5-4.5 times the burnup value of the CANDU-37 reactor fed with the NatUO2 fuel. The results of this study bring out that in terms of energy production, the CANDU-37 reactor fuelled with the ThO2 and spent UO2 fuels enriched in ADS designs demonstrates higher neutronic performance than the conventional CANDU-37 reactor.
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来源期刊
Nuclear Technology & Radiation Protection
Nuclear Technology & Radiation Protection NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.00
自引率
41.70%
发文量
10
审稿时长
6-12 weeks
期刊介绍: Nuclear Technology & Radiation Protection is an international scientific journal covering the wide range of disciplines involved in nuclear science and technology as well as in the field of radiation protection. The journal is open for scientific papers, short papers, review articles, and technical papers dealing with nuclear power, research reactors, accelerators, nuclear materials, waste management, radiation measurements, and environmental problems. However, basic reactor physics and design, particle and radiation transport theory, and development of numerical methods and codes will also be important aspects of the editorial policy.
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