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Analysis on Plutonium Production In Fast Breeder Reactor (FBR) Cycle Based on Transuranium Fuel Loading

机译:基于铀燃料负荷的快中子反应堆(FBR)循环中Production的生产分析

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摘要

Nuclear reactor can provide some fissile materials by them self as breeder from converted fertile materials during reactor operation. Plutonium production becomes one of the important aspect in relation with recycling material of transuranic materials. Plutonium recycling program as good candidate for fuel optimization program, gives an issue of nuclear proliferation resistance due to its potential to be used as fuel for explosive devices. How to maintain higher capability of fuel breeding in the reactors should be followed by reducing the risk of nuclear proliferation such as plutonium material. As one of the important aspects from intrinsic nuclear proliferation resistance view point, level of material barrier as one of the control material which is related to higher technical difficulties (barrier) based on more complex design of nuclear explosive and fuel handling. Minor actinides (MA) as one of the recycled spent nuclear fuel, have been used and developed to be recycled for some purposes such as converted fuel for extending longer reactor operation, burning and transmutation of MA, fuel breeding of FBR as well as for proliferation resistance purposes [1-10]. In this present study, plutonium production based on transuranium fuel loading in fast breeder reactor (FBR) has been evaluated. Plutonium production can be evaluated based on fuel production as sustainable aspect as well as plutonium proliferation aspect of the reactors.
机译:核反应堆可以在反应堆运行期间通过转化后的肥沃材料自身作为育种者来提供一些裂变材料。 trans的生产成为与超铀材料的回收材料相关的重要方面之一。 fuel回收计划是燃料优化计划的良好选择,但由于其可能用作爆炸装置的燃料,因此产生了抗核扩散的问题。如何在反应堆中保持更高的燃料繁殖能力,应继之以减少诸如nuclear材料之类的核扩散风险。从内在的核扩散阻力观点来看,作为重要的方面之一,基于更复杂的核爆炸物和燃料处理设计,作为控制材料之一的材料屏障水平与更高的技术难度(屏障)有关。次要act系元素(MA)是一种循环利用的废核燃料,已被开发用于某些目的,例如转化燃料以延长反应堆的运行时间,MA的燃烧和trans变,FBR的燃料育种以及扩散抵抗的目的[1-10]。在本研究中,已经评估了基于快速增殖反应堆(FBR)中铀燃料负荷的p生产。 fuel的生产可以基于燃料生产作为反应堆可持续性方面以及evaluated扩散方面进行评估。

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  • 会议地点 Santa Fe(US)
  • 作者单位

    Bandung Institute of Technology, J1. Ganesha 10, Bandung,West java, 40151, Indonesia,;

    Bandung Institute of Technology, J1. Ganesha 10, Bandung,West java, 40151, Indonesia,;

    Nuclear Energy Regulatory, J1 Gajah Mada No. 8, PO.BOX 4005 Jakarta 10040 Indonesia;

    Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 Japan;

    Tokyo Institute of Technology, 2-12-1 O-Okayama, Meguro-ku, Tokyo 152-8550, Japan;

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  • 正文语种 eng
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  • 入库时间 2022-08-26 14:13:20

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