Xenon Recovery from Molybdenum-99 Production

Robert T. Jubin , Patricia D. Paviet , James C. Bresee
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引用次数: 1

Abstract

The U.S. Department of Energy Office of Nuclear Energy (DOE-NE) sponsors research and development on the recycle of used commercial nuclear fuel as an option for future nuclear fuel cycles that offers increased use of uranium and thorium resources and a possible reduction in the overall cost of nuclear waste management. The two alternatives, direct disposal of used fuel and fuel recycle, are broadly referred to as open and closed fuel cycles. One requirement of a closed fuel cycle is the safe management of radioactive off-gases, which includes 14C, radioiodine and the noble gases, including radioxenon. The longest lived relevant radioxenon isotope is 127Xe; with a half-life of just 36.35 days it is feasible to trap and hold the radioxenon to allow for decay to safe environmental levels. However, the very weak chemical bonds of noble gases, in this case xenon, make them difficult to trap, which led to an extensive DOE-NE study of noble gas adsorption on various molecular sieves as an alternative to costly cryogenics processes. Preliminary results indicate that xenon adsorption at near room temperature on molecular sieves, both synthetic and natural, may have both cost and efficiency advantages over cryogenic processes.

Xenon radioisotopes with short half-lives have value in the detection of underground nuclear explosions. However radioxenon released by medical isotope production facilities produces high backgrounds that complicate its use for nuclear explosion detection. Specifically, recovery of 99Mo for medical applications from short-cooled irradiated 235U targets results in the release of some radioxenon. In March 2015, by a unanimous vote of the five permanent members of the United Nations Security Council, commercial producers of 99Mo were asked to decrease and, if possible, eliminate the emissions of radioactive xenon from their production processes. The use of materials currently being evaluated for Xe and Kr capture for use in UNF processing applications may provide a cost effective mechanism to achieve the United Nations Security Council goal.

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钼-99生产中氙的回收
美国能源部核能办公室(DOE-NE)赞助对使用过的商业核燃料的再循环进行研究和开发,将其作为未来核燃料循环的一种选择,从而增加铀和钍资源的使用,并有可能降低核废料管理的总成本。两种替代方案,即使用过的燃料的直接处置和燃料的再循环,被广泛地称为开放式和封闭式燃料循环。闭式燃料循环的一个要求是放射性废气的安全管理,其中包括14C、放射性碘和惰性气体,包括放射性氙。寿命最长的放射性氙同位素是127Xe;由于放射性氙的半衰期只有36.35天,因此可以捕获并保存它,使其衰变到安全的环境水平。然而,稀有气体(在本例中为氙)的化学键非常弱,使得它们难以捕获,这导致了对稀有气体在各种分子筛上的吸附作为昂贵的低温工艺的替代方案的广泛研究。初步结果表明,在接近室温的情况下,氙气在分子筛上的吸附,无论是合成的还是天然的,都可能比低温过程具有成本和效率上的优势。半衰期短的氙放射性同位素对地下核爆炸的探测有价值。然而,医疗同位素生产设施释放的放射性氙产生高背景,使其用于核爆炸探测变得复杂。具体来说,从短冷辐照的235U靶中回收用于医疗用途的99Mo会导致一些放射性氙的释放。2015年3月,联合国安理会(United Nations Security Council)五个常任理事国一致投票,要求99Mo的商业生产商减少并尽可能消除其生产过程中放射性氙的排放。利用目前正在评价的Xe和Kr捕获材料用于联合国自然资源处理应用,可能为实现联合国安全理事会的目标提供一种成本效益高的机制。
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