Irradiation performance and first examinations of Americium bearing blanket fuel from the MARINE irradiation experiment

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2023-08-25 DOI:10.1016/j.jnucmat.2023.154699

S. van Til , P.R. Hania , A.V. Fedorov , E. D'Agata , D. Freis , S. Bejaoui , F. Delage , A. Gallais-During

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引用次数: 0

Abstract

Americium (Am) is a strong contributor to the long-term radiotoxicity of high-level waste from nuclear fuels. Transmutation of long-lived nuclides like ²⁴¹Am by irradiation in nuclear reactors is therefore an option for the reduction of radiotoxicity and heat production of waste volumes to be stored in a repository. The MARINE irradiation experiment is the latest in a series of European experiments on americium transmutation (e.g. EFTTRA-T4, EFTTRA-T4bis, HELIOS, MARIOS, SPHERE) performed in the High Flux Reactor (HFR) in Petten (The Netherlands). The development and irradiation of MARINE was carried out in the framework of the collaborative research project PELGRIMM of the EURATOM 7th Framework Programme (FP7). Dismantling was completed and post-irradiation examinations (PIE) were started within the Dutch national research programme PIONEER. Destructive PIE is foreseen within the Euratom H2020 funded project PATRICIA.

The main objective of the MARINE experiment is to study the in-pile behaviour of uranium oxide fuel containing 13% of americium and to compare the behaviour of sphere-pac versus pellet fuel, in particular the role of microstructure and temperature on fission gas and helium release dynamics on fuel swelling.

The MARINE experiment was irradiated for 359 Full Power Days in the HFR in 2016 and 2017. This paper discusses results from irradiation, i.e. power and temperature history and transmutation rates as well as preliminary results from post irradiation examinations, assessing a.o. clad strains and helium and fission gas release and first ceramographic observations, putting a preliminary upper bound on fuel swelling.

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海洋辐照试验中含镅包层燃料的辐照性能及初步检验

镅(Am)是核燃料产生的高放废物的长期放射性毒性的重要贡献者。因此，在核反应堆中通过辐照使长寿命核素(如241Am)发生嬗变，是减少储存在储存库中的大量废物的放射性毒性和产热的一种选择。海洋辐照实验是欧洲在Petten(荷兰)的高通量反应堆(HFR)中进行的一系列关于镅嬗变的实验(例如eftra - t4, eftra - t4 bis, HELIOS, MARIOS, SPHERE)中的最新实验。MARINE的开发和辐照是在欧洲原子能机构第7框架计划(FP7)的合作研究项目PELGRIMM的框架内进行的。拆除工作已完成，辐照后检查(PIE)在荷兰国家研究方案PIONEER范围内开始。破坏性PIE预计将在欧洲原子能机构H2020资助的PATRICIA项目中进行。MARINE实验的主要目的是研究含有13%镅的氧化铀燃料的堆内行为，并比较球形pac和颗粒燃料的行为，特别是微观结构和温度对裂变气体和氦释放动力学对燃料膨胀的作用。MARINE实验于2016年和2017年在HFR中照射了359个满功率日。本文讨论了辐照的结果，即功率和温度历史和嬗变率，以及辐照后检查的初步结果，评估了a.o.包层应变和氦和裂变气体释放，以及第一次陶粒观测，对燃料膨胀给出了初步上限。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.