Fabrication of U-10wt.%Zr-RE Fuel Slugs by Recycling of Metallic Fuel Scraps

• Autorzy: Kim Ki-Hwan , Mun Seung-Uk , Ha Seong-Jun , Kuk Seoung-Woo , Park Jeong-Yong

Identyfikatory

DOI

10.24425/amm.2020.133213

• Języki publikacji: EN

Abstrakty

EN

U-10wt.%Zr-5wt.%RE fuel slugs for a sodium-cooled fast reactor (SFR) were conventionally prepared by a modified injection casting method, which had the drawback of a low fabrication yield rate of approximately 60% because of the formation of many metallic fuel scraps, such as melt residue and unsuitable fuel slug butts. Moreover, the metallic fuel scraps were classified as a radioactive waste and stored in temporary storage without recycling. It is necessary to develop a recycling process technology for scrap wastes in order to reduce the radioactive wastes of the fuel scraps and improve the fabrication yield of the fuel slugs. In this study, the additive recycling process of the metallic fuel scraps was introduced to re-fabricate the U-10wt.%Zr-5wt.%RE fuel slugs. The U-10wt.%Zr-5wt.%RE fuel scraps were cleaned on the surface impurity layers with a mechanical treatment that used an electric brush under an Ar atmosphere. The U-10wt.%Zr-5wt.%RE fuel slugs were soundly re-fabricated and examined to evaluate the feasibility of the additive process compared with the metallic fuel slugs that used pure metals.

Słowa kluczowe

EN

fuel slug; scrap recycling; mechanical cleaning treatment; fabrication yield rate; radioactive wastes

• 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: 2020
• Tom: Vol. 65, iss. 3
• Strony: 1035--1039
• Opis fizyczny: Bibliogr. 25 poz., fot., rys., tab.

Twórcy

autor

Kim Ki-Hwan

• Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, Daejeon, 34507, Republic of Korea

autor

Mun Seung-Uk

• Sungkyunkwan University, Advanced Materials Science & Engineering Department, Suwon, 16419, Republic of Korea

autor

Ha Seong-Jun

• Yonsei University, Department of Materials Science and Engineering, Seoul, 03722, Republic of Korea

autor

Kuk Seoung-Woo

• Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, Daejeon, 34507, Republic of Korea

autor

Park Jeong-Yong

• Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, Daejeon, 34507, Republic of Korea

Bibliografia

• [1] H. S. Lee, G. I. Park, I. J. Cho, Sci. Technol. Nucl. Install. 2013, 1-11 (2013).
• [2] J. I. Jang, Nucl. Eng. Technol. 43, 161-170 (2007).
• [3] J. Karmack, K. O. Pasamehmetoglu, D. Alberstein, Assessment of startup fuel options for the GNEP Advanced Burner Reactor (ABR), INL/EXT-08-13773.
• [4] H. S. Lee, G. I. Park, E. H. Kim, Nucl. Eng. Technol. 43, 317-328 (2011).
• [5] D. E. Burkes, R. S. Fielding, D. L. Porter, D. C. Crawford, M. K. Meyer, J. Nucl. Mater. 389, 458-469 (2009).
• [6] L. C. Walters, J. Nucl. Mater. 207, 39-48 (1999).
• [7] J. H. Jang, H. S. Kang, Y. S. Lee, H. S. Lee, J. D. Kim, J. Radioanal. Nucl. Chem. 295, 1743-1751 (2013).
• [8] C. B. Lee, J. S. Cheon, S. H. Kim, J. Y. Park, H. K. Joo, Nucl. Eng. Technol. 48, 1096-1108 (2016).
• [9] D. C Crawford, D. L. Porter, S. L. Hayes, J. Nucl. Mater. 371, 202-231 (2007).
• [10] J. H. Kim, H. Song, H. T. Kim, K. H. Kim, C. B. Lee, R. S. Fielding, J. Radioanal. Nucl. Chem. 299, 103-109 (2014).
• [11] J. H. Kim, K. H. Kim, C. B. Lee, Adv. Mater. Sci. Eng. 2015, 1-8 (2015).
• [12] S. W. Kuk, K. H. Kim, J. H. Kim, H. Song, S. J. Oh, J. Y. Park, C. B. Lee, Y. S. Youn, J. Y. Kim, J. Nucl. Mater. 486, 53-59 (2017).
• [13] S. J. Ha, K. H. Kim, J. Y. Park, S. I. Hong, Sci. Adv. Mater. 9, 1837-1841 (2017).
• [14] K. H. Kim, S. J. Ha, J. Y. Park, S. J. Oh, S. H. Kim, in: Proceedings of the American Nuclear Annual Meeting, U.S.A (2018).
• [15] J. H. Kim, H. T. Kim, K. H. Kim, C. B. Lee, J. Radioanal. Nucl. Chem. 300, 1245-1251 (2014).
• [16] J. H. Kim H. Song, K. H. Kim, C. B. Lee, Surf. Interface Anal. 47, 301-307 (2015).
• [17] K. H. Kim, C. T. Lee, C. B. Lee, R. S. Fielding, J. R. Kennedy, J. Nucl. Mater. 441, 535-538 (2013).
• [18] J. H. Kim, J. W. Lee, K. H. Kim, J. Y. Park, J. Nucl. Sci. Technol. 54, 648-654 (2017).
• [19] S. H. Lee, K. H. Kim, S. W. Kuk, J. Y. Park, J. H. Choi, Arch. Metall. Mater. 64, 953-957 (2019).
• [20] J. H. Kim H. Song, K. H. Kim, C. B. Lee, J. Radioanal. Nucl. Chem. 301, 797-803 (2014).
• [21] F. A Rough, Report No. BMI-1030, Battelle Memorial Institute, Metallurgy and ceramics, M-3697, 16th Ed. (1955).
• [22] D. E. Janney, J. R. Kennedy, Mater. Charact. 61, 1194-1202 (2010).
• [23] D. E. Janney, T. P. O’Holleran, J. Nucl. Mater. 460, 13-15 (2015).
• [24] S. J. Ha, K. H. Kim, J. Y. Park, S. I. Hong, J. Radioanal. Nucl. Chem. 316, 1157-1163 (2014).
• [25] K. H. Kim, S. J. Ha, S. J. Oh, S. W. Kuk, J. Y. Park, in: Proceedings of the Korean Spring Radioactive Waste Meeting, Republic of Korea (2018).

Uwagi

EN

1. This work was carried out under the Nuclear Research and Development Program supported by the Ministry of Science and Technology in the Republic of Korea.

PL

2. Opracowanie rekordu ze środków MNiSW, umowa Nr 461252 w ramach programu "Społeczna odpowiedzialność nauki" - moduł: Popularyzacja nauki i promocja sportu (2020).