Development of NdYO₃ Powder Fabrication as a Reaction Preventing Raw Material for Metal Fuel Casting

• Autorzy: Park Sang-Gyu , Kim Ki-Hwan , Kim Jun Hwan

Identyfikatory

DOI

10.24425/amm.2024.149760

• Języki publikacji: EN

Abstrakty

EN

Metal fuel is a promising candidate for the pyro-processed nuclear fuel, but the problem of loss of nuclear material due to the high reactivity of metal fuel and melting crucible in the metal fuel casting process must be solved for loss control and waste reduction. In this study, fabrication test was conducted to develop a new material NdYO₃ as a new crucible material to improve the degree of anti-reactivity. The NdYO₃ compact was manufactured by the CIP (Cold isostatic pressing) method with changing fraction of Nd₃O₃ and Y₂O₃ powders. Sintering process was performed at 1550°C for 10 hours. The systematic trends of XRD patterns shows that phase transformations form cubic structure to monoclinic structures occurred with the addition of Y₂O₃. The rate of pore were discussed with change of fraction of Nd₂O₃ and Y₂O₃.

Słowa kluczowe

EN

metal fuel; reaction prevention; Y2O3; NdYO3; sintering

• Wydawca: Institute of Metallurgy and Materials Science of Polish Academy of Sciences ; Committee of Materials Engineering and Metallurgy of Polish Academy of Sciences
• Czasopismo: Archives of Metallurgy and Materials
• Rocznik: 2024
• Tom: Vol. 69, iss. 2
• Strony: 429--432
• Opis fizyczny: Bibliogr. 7 poz., fot., rys., tab.

Twórcy

autor

Park Sang-Gyu

• Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, 989-111, Daedeok-daero, Yuseong-gu, Daejeon, 34057, Republic of Korea

• https://orcid.org/0000-0002-7939-0341

autor

Kim Ki-Hwan

• Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, 989-111, Daedeok-daero, Yuseong-gu, Daejeon, 34057, Republic of Korea

• https://orcid.org/0000-0002-4861-4330

autor

Kim Jun Hwan

• Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, 989-111, Daedeok-daero, Yuseong-gu, Daejeon, 34057, Republic of Korea

• https://orcid.org/0009-0005-4125-0051

Bibliografia

• [1] T. Abram, S. Ion, Energy Policy 36, 4323-4330 (2008).
• [2] Generation IV International Forum, A Technology Roadmap for Generation IV Nuclear Energy Systems, 2002.
• [3] H. Lee, G.I. Park, E.H. Kim, Nucl. Eng. Technol. 43, 317-328 (2011).
• [4] J.I. Jang, Nucl. Eng. Technol. 43, 161-170 (2007).
• [5] G. Ledergerber, F. Ingold, R.W. Stratton et al., Nucl. Tech. 114, 194-203 (1996).
• [6] G. Bart, F.B. Botta, C.W. Hoth, G. Ledergerber, R.E. Mason, R.W. Stratton, J. Nucl. Mater. 376, 47-59 (2008).
• [7] S. Huang, O.V. Biest, J. Vleugelsw, J. Am. Ceram. Soc. 89, 2596-2601 (2006).

Uwagi

This work was supported by the National Nuclear R&D program funded by Ministry of Science and ICT (RS-2022-00155198).