A. Chakraborty , P.S. Ghosh , N. Choudhury , A. Arya
{"title":"Thermal and diffusional properties of uranium-americium and plutonium-americium mixed oxides","authors":"A. Chakraborty , P.S. Ghosh , N. Choudhury , A. Arya","doi":"10.1016/j.jnucmat.2025.156152","DOIUrl":null,"url":null,"abstract":"<div><div>The knowledge of thermo-physical and transport properties of mixed oxide fuels containing minor actinides such as Americium (Am) and Neptunium (Np) is of paramount importance in the front end of the nuclear fuel cycle. Because of the radiotoxic nature of these materials, a priory evaluation of these properties using theoretical and computational means is immensely useful. In the present work, various thermal and diffusional properties, like, thermal expansion, specific heats, thermal conductivity, and oxygen vacancy migration barriers of U<span><math><msub><mrow></mrow><mrow><mn>1</mn><mo>−</mo><mi>y</mi></mrow></msub></math></span>Am<sub><em>y</em></sub>O<sub>2</sub> and Pu<span><math><msub><mrow></mrow><mrow><mn>1</mn><mo>−</mo><mi>y</mi></mrow></msub></math></span>Am<sub><em>y</em></sub>O<sub>2</sub> mixed oxides (MOX) are determined by extensive molecular dynamics (MD) simulations. Unlike most of the previous MD simulation studies, the present work explicitly considers the effect of different oxidation states, such as U<sup>+4</sup>, U<sup>+5</sup> and Am<sup>+3</sup>, by using a new interatomic potential to evaluate the thermal properties of U<span><math><msub><mrow></mrow><mrow><mn>1</mn><mo>−</mo><mi>y</mi></mrow></msub></math></span>Am<sub><em>y</em></sub>O<sub>2</sub> MOX. For linear thermal expansion, the results obtained by using new interatomic potential in U<span><math><msub><mrow></mrow><mrow><mn>1</mn><mo>−</mo><mi>y</mi></mrow></msub></math></span>Am<sub><em>y</em></sub>O<sub>2</sub> with 0 ≤ y ≤ 0.3125 and Pu<span><math><msub><mrow></mrow><mrow><mn>1</mn><mo>−</mo><mi>y</mi></mrow></msub></math></span>Am<sub><em>y</em></sub>O<sub>2</sub> are in excellent agreement with those obtained from the experimental studies. The peaks in the thermal expansion coefficient (<em>α</em>) and specific heat (<span><math><msub><mrow><mi>C</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span>) versus temperature plots originated due to the Bredig transition in U<span><math><msub><mrow></mrow><mrow><mn>1</mn><mo>−</mo><mi>y</mi></mrow></msub></math></span>Am<sub><em>y</em></sub>O<sub>2</sub> MOX shifts towards lower temperature as y increases up to 0.3125. This is qualitatively consistent with an almost linear decrease of the melting points with the increase in y as observed in experiments. The MD calculated <em>α</em> and <span><math><msub><mrow><mi>C</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span> values of U<span><math><msub><mrow></mrow><mrow><mn>1</mn><mo>−</mo><mi>y</mi></mrow></msub></math></span>Am<sub><em>y</em></sub>O<sub>2</sub> MOX (for <span><math><mn>0</mn><mo><</mo><mi>y</mi><mo><</mo><mn>0.3125</mn></math></span>) are fitted to the Bathellier equation which can be used to determine high temperature behavior of the MOX fuel where no experimental data is available. The impact on the thermal conductivity (TC) for the introduction of AmO<sub>2</sub> into UO<sub>2</sub> is much stronger than that of the introduction of the same into PuO<sub>2</sub>. Depending on the temperature, reduction in TC is in the range of 27.0–2.5% when 12.5 atom% AmO<sub>2</sub> is added in UO<sub>2</sub> as compared to 13.5-2.3% reduction in case of 12.5 atom% AmO<sub>2</sub> incorporated PuO<sub>2</sub>. Based on the migration energies and vacancy-solute interaction energy, the concentration dependence of the mean square deviation in MOX is explained. A schematic of high oxygen diffusivity regions in MOX is also identified.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156152"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002231152500546X","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0
Abstract
The knowledge of thermo-physical and transport properties of mixed oxide fuels containing minor actinides such as Americium (Am) and Neptunium (Np) is of paramount importance in the front end of the nuclear fuel cycle. Because of the radiotoxic nature of these materials, a priory evaluation of these properties using theoretical and computational means is immensely useful. In the present work, various thermal and diffusional properties, like, thermal expansion, specific heats, thermal conductivity, and oxygen vacancy migration barriers of UAmyO2 and PuAmyO2 mixed oxides (MOX) are determined by extensive molecular dynamics (MD) simulations. Unlike most of the previous MD simulation studies, the present work explicitly considers the effect of different oxidation states, such as U+4, U+5 and Am+3, by using a new interatomic potential to evaluate the thermal properties of UAmyO2 MOX. For linear thermal expansion, the results obtained by using new interatomic potential in UAmyO2 with 0 ≤ y ≤ 0.3125 and PuAmyO2 are in excellent agreement with those obtained from the experimental studies. The peaks in the thermal expansion coefficient (α) and specific heat () versus temperature plots originated due to the Bredig transition in UAmyO2 MOX shifts towards lower temperature as y increases up to 0.3125. This is qualitatively consistent with an almost linear decrease of the melting points with the increase in y as observed in experiments. The MD calculated α and values of UAmyO2 MOX (for ) are fitted to the Bathellier equation which can be used to determine high temperature behavior of the MOX fuel where no experimental data is available. The impact on the thermal conductivity (TC) for the introduction of AmO2 into UO2 is much stronger than that of the introduction of the same into PuO2. Depending on the temperature, reduction in TC is in the range of 27.0–2.5% when 12.5 atom% AmO2 is added in UO2 as compared to 13.5-2.3% reduction in case of 12.5 atom% AmO2 incorporated PuO2. Based on the migration energies and vacancy-solute interaction energy, the concentration dependence of the mean square deviation in MOX is explained. A schematic of high oxygen diffusivity regions in MOX is also identified.
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.