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THE ATTRACTIVENESS OF MATERIALS ASSOCIATED WITH THORIUM BASED NUCLEAR FUEL CYCLES FOR PHWR'S

机译:WR基核燃料循环中PH材料对PHWR的吸引力

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This paper reports the continued evaluation of the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with thorium based nuclear fuel cycles. Specifically, this paper examines a thorium fuel cycle in which a pressurized heavy water reactor (PHWR) is fueled with mixtures of natural uranium/ U/thorium. These mixtures would be most beneficial for the export of fuel from a nation-state with a cradle-to-grave nuclear policy to developing countries interested in utilizing 2-3 reactors for power. This paper uses a PHWR fueled with natural uranium as a base fuel cycle, and then compares material attractiveness of fuel cycles that use ~(233)U/thorium salted with natural uranium. The results include the material attractiveness of fuel at beginning of life (BoL), end of life (EoL), and the number of fuel assemblies required to collect a bare critical mass of plutonium or uranium. This study indicates what is required to render the uranium as having low utility for use in nuclear weapons; in addition, this study estimates the increased number of assemblies required to accumulate a bare critical mass of plutonium that has a higher utility for use in nuclear weapons. This approach identifies that some fuel cycles may be easier to implement the International Atomic Energy Agency (IAEA) safeguards approach and have a more effective safeguards by design outcome. For this study, approximately one year of fuel is required to be reprocessed to obtain one bare critical mass of plutonium. Nevertheless, the result of this paper suggests that all spent fuel needs to be rigorously safeguarded and provided with high levels of physical protection. This study was performed at the request of the United States Department of Energy /National Nuclear Security Administration (DOE/NNSA). The methodology and key findings will be presented.
机译:本文报告了继续评估与special基核燃料循环相关的含特殊核材料(SNM)的材料混合物的吸引力。具体而言,本文研究了or燃料循环,其中使用天然铀/ U / th的混合物为加压重水反应堆(PHWR)进行燃料供给。这些混合物将最有利于从具有从摇篮到坟墓的核政策的民族国家向有兴趣利用2-3个反应堆供电的发展中国家的燃料出口。本文使用以天然铀为燃料的PHWR作为基本燃料循环,然后比较使用〜(233)U / th与天然铀一起盐化的th的燃料循环的材料吸引力。结果包括寿命开始时(BoL),寿命结束(EoL)时燃料的材料吸引力以及收集to或铀的裸露临界质量所需的燃料组件数量。这项研究表明,要使铀在核武器中的实用性低,需要采取什么措施;此外,这项研究估计,积累用于核武器的实用性更高的裸critical临界质量的required所需的组件数量也将增加。这种方法表明,某些燃料循环可能更易于实施国际原子能机构(IAEA)的保障措施,并根据设计结果具有更有效的保障措施。对于本研究,大约需要一年的燃料才能进行后处理,以获得one的临界临界质量。尽管如此,本文的结果表明,所有乏燃料都必须得到严格保护,并提供高水平的实物保护。这项研究是应美国能源部/国家核安全局(DOE / NNSA)的要求进行的。将介绍方法和主要发现。

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