辐照UO2燃料中铯和碘的形态

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-04-01 Epub Date: 2025-02-26 DOI:10.1016/j.jnucmat.2025.155715
J.-Y. Colle , J.N. Zappey , O. Beneš , M. Cologna , T. Wiss , R.J.M. Konings
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引用次数: 0

摘要

核燃料中CsI的存在一直备受争议。它的形成大大降低了挥发性,从而降低了在核事故中从反应堆堆芯释放碘和铯的速度。用克努森液质谱法(KEMS)对一系列样品进行了研究,以确定辐照核燃料中是否存在CsI。检测的样品包括纯CsI、暴露于伽马辐射的CsI、掺CsI的UO2模拟燃料和辐照过的轻水堆燃料样品。考察了CsI和CsI掺杂样品,建立了keems检测CsI的边界条件。这些样品表明,燃料中CsI的存在由Cs+、I+和CsI+三个质谱信号表征,CsI+和I+的峰值比为1:7 . 0。对辐照燃料的检查没有发现这些特征,因此没有证据表明,至少在贮存多年后,在辐照过的轻水堆核燃料中存在CsI。
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Cesium and iodine speciation in irradiated UO2 fuel
The presence of CsI in nuclear fuel has long been debated. Its formation significantly decreases volatility, thereby reducing the rate at which iodine and cesium are released from the reactor core during a nuclear accident. A series of samples were investigated by Knudsen Effusion Mass Spectrometry (KEMS) in order to determine whether CsI is present in irradiated nuclear fuel. The examined samples were pure CsI, CsI exposed to gamma radiation, CsI-doped UO2 simulated fuel and irradiated LWR fuel samples. The CsI and CsI-doped samples were examined to establish boundary conditions for the detection of CsI by KEMS. These samples indicated that the presence of CsI in fuel is characterized by three mass spectrometric signals Cs+, I+ and CsI+, with a peak ratio of CsI+ and I+ of 1:0.7. The examinations of irradiated fuels showed none of these characteristics and hence no evidence that CsI is present in irradiated LWR nuclear fuel, at least after a storage period of years.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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