A. Chakraborty , P.S. Ghosh , N. Choudhury , A. Arya
{"title":"铀-镅和钚-镅混合氧化物的热特性和扩散特性","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":"{\"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}","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
摘要
在核燃料循环的前端,对含有少量锕系元素如镅(Am)和镎(Np)的混合氧化物燃料的热物理和输运性质的了解是至关重要的。由于这些材料的放射性毒性,使用理论和计算方法对这些特性进行先验评估是非常有用的。在本工作中,通过广泛的分子动力学(MD)模拟,确定了U1−yAmyO2和Pu1−yAmyO2混合氧化物(MOX)的各种热和扩散性质,如热膨胀、比热、导热系数和氧空位迁移势垒。与以往的MD模拟研究不同,本研究明确考虑了不同氧化态的影响,如U+4, U+5和Am+3,通过使用新的原子间电位来评估U1−yAmyO2 MOX的热性能。对于线性热膨胀,利用U1−yAmyO2中0≤y≤0.3125和Pu1−yAmyO2中新的原子间势得到的结果与实验研究结果非常吻合。当y增大到0.3125时,U1−yAmyO2 MOX中Bredig跃迁引起的热膨胀系数(α)和比热(Cp)随温度的变化峰向低温方向移动。这与实验中观察到的熔点随着y的增加几乎呈线性下降的现象在质量上是一致的。MD计算的U1−yAmyO2 MOX (0<y<0.3125)的α和Cp值拟合到Bathellier方程,该方程可用于确定没有实验数据的MOX燃料的高温行为。在UO2中引入AmO2对热导率(TC)的影响远大于在PuO2中引入AmO2。当UO2中加入12.5原子%的AmO2时,TC的还原率在27.0 ~ 2.5%之间,而当UO2中加入12.5原子%的AmO2时,TC的还原率为13.5 ~ 2.3%,这取决于温度。基于迁移能和空溶质相互作用能,解释了MOX中均方差的浓度依赖性。还确定了MOX中高氧扩散率区域的示意图。
Thermal and diffusional properties of uranium-americium and plutonium-americium mixed oxides
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.