Analysis of neptunium oxides produced through modified direct denitration

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2023-08-29 DOI:10.1016/j.jnucmat.2023.154704
Kathryn M. Peruski, Connor J. Parker, Samantha K. Cary
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引用次数: 1

Abstract

Production of neptunium-237 (237Np) target materials for plutonium-238 (238Pu) radioisotope thermoelectric generators (RTGs) for deep space exploration requires advanced chemistry and engineering development. Currently, the domestic Pu-238 Supply Program at Oak Ridge National Laboratory produces neptunium dioxide (NpO2) for target material using a modified direct denitration (MDD) flowsheet. Although the chemistry, reaction mechanisms, and product characteristics of MDD are well understood for uranium, corresponding studies of the neptunium system are still needed to continue optimization of target material properties, production equipment design, and production flowsheets. The objective of this work is to characterize crystalline phases, morphology, surface texture, and particle size of NpO2 produced via MDD reactions. Solid-phase characterization techniques, including powder X-ray diffraction (pXRD) and scanning electron microscopy with energy-dispersive spectroscopy (SEM-EDS), were employed to achieve this objective. Subsequent data processing using the Morphological Analysis for Material Attribution (MAMA) software was performed to analyze particle morphology and size. Broadly, the powders were found to contain a mixture of NpO2 and Np2O5 after denitration with a variety of morphologies. After high-firing, the product was found to be NpO2 with a typical polycrystalline oxide morphology and a grain size ranging from 0.72 to 0.94 µm. These analyses provide knowledge on the reaction pathway for a non-traditional NpO2 synthesis method and offer additional unique insight into production-scale environments for transuranic materials.

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改性直接脱硝法生产氧化镎的分析
生产用于深空探测的钚-238 (238Pu)放射性同位素热电发生器(rtg)的镎-237 (237Np)靶材料需要先进的化学和工程发展。目前,橡树岭国家实验室的国内Pu-238供应计划使用改进的直接脱硝(MDD)流程为目标材料生产二氧化镎(NpO2)。虽然对铀的MDD的化学性质、反应机理和产物特性已经有了很好的了解,但仍需要对镎体系进行相应的研究,以继续优化目标材料的性能、生产设备的设计和生产流程。本研究的目的是表征通过MDD反应生成的NpO2的晶相、形貌、表面结构和粒度。固相表征技术,包括粉末x射线衍射(pXRD)和扫描电子显微镜与能量色散光谱(SEM-EDS),被用来实现这一目标。随后使用材料归因形态学分析(MAMA)软件进行数据处理,分析颗粒形态和大小。总的来说,脱硝后的粉末含有NpO2和Np2O5的混合物,具有多种形态。经高温焙烧后,产物为NpO2,具有典型的多晶氧化物形态,晶粒尺寸在0.72 ~ 0.94µm之间。这些分析为非传统NpO2合成方法的反应途径提供了知识,并为超铀材料的生产规模环境提供了额外的独特见解。
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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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