Characterization of Cladding Hull Wastes from Used Nuclear Fuels

• Autorzy: Kang K. H. , Lee C. H. , Jeon M. K. , Han S. Y. , Park G. I. , Hwang S.-M.

Identyfikatory

DOI

10.1515/amm-2015-0097

Warianty tytułu

PL

Charakterystyka odpadów z okładzin reaktora wodnego ciśnieniowego

• Języki publikacji: EN

Abstrakty

EN

Used cladding hulls from pressurized water reactor (PWR) are characterized to provide useful information for the treatment and disposal of cladding hull wastes. The radioactivity and the mass of gamma emitting nuclides increases with an increase in the fuel burn-up and their removal ratios are found to be more than 99 wt.% except Co-60 and Cs-137. In the result of measuring the concentrations of U and Pu included in the cladding hull wastes, most of the residues are remained on the surface and the removal ratio of U and Pu are revealed to be over 99.98 wt.% for the fuel burn-up of 35,000 MWd/tU. An electron probe micro-analyzer (EPMA) line scanning shows that radioactive fission products are penetrated into the Zr oxide layer, which is proportional to the fuel burn-up. The oxidative decladding process exhibits more efficient removal ratio of radionuclides.

Słowa kluczowe

EN

used nuclear fuels; metal waste; cladding hulls; zircaloy; radioactivity

PL

reaktor wodny ciśnieniowy; odpady metalowe; odpady z okładzin; radioaktywność

• 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: 2015
• Tom: Vol. 60, iss. 2B
• Strony: 1199--1203
• Opis fizyczny: Bibliogr. 13 poz., rys.

Twórcy

autor

Kang K. H.

• Nuclear Fuel Cycle Process Process Development Division, Korea Atomic Energy Research Institute, 989-11 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea

autor

Lee C. H.

• Nuclear Fuel Cycle Process Process Development Division, Korea Atomic Energy Research Institute, 989-11 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea

autor

Jeon M. K.

• Nuclear Fuel Cycle Process Process Development Division, Korea Atomic Energy Research Institute, 989-11 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea

autor

Han S. Y.

• Nuclear Fuel Cycle Process Process Development Division, Korea Atomic Energy Research Institute, 989-11 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea

autor

Park G. I.

• Nuclear Fuel Cycle Process Process Development Division, Korea Atomic Energy Research Institute, 989-11 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea

autor

Hwang S.-M.

• Hydrogen and Fuel Cell Department, Korea Institute of Energy Research, 152, Gajeong-Ro, Yuseong-Gu, Daejeon 305-343, Republic of Korea

Bibliografia

• [1] H. Lee, G. I. Park, K. H. Kang, J. M. Hur, J. G. Kim, D. H. Ahn, Y. Z. Cho, E. H. Kim, Nucl. Eng. Technol. 43, 317 (2011).
• [2] K. C. Song, H. Lee, J. M. Hur, J. G. Kim, D. H. Ahn, Y. Z. Cho, Nucl. Eng. Technol. 42, 131 (2010).
• [3] J. J. Laidler, J. E. Battles, W. E. Miller, J. P. Ackerman, E. L. Carls, Prog. Nucl. Energ. 31, 131 (1997).
• [4] K. H. Kang, C. H. Lee, M. K. Jeon, Y. L. Lee, Y. T. Choi, G. I. Park, Treatment Technology of Hull Wastes, KAERI/TR-5288, 2013.
• [5] M. Nutt et al., Information Basis for Developing Comprehensive Waste Management System - US-Japan Joint Nuclear Energy Action Plan Waste Management Working Group Phase I Report, FCR&D-USED-2010-000051, 2010.
• [6] R. Restani, E. T. Aerne, G. Bart, H. P. linder, A. Muller, F. Petrik, Characterisation of PWR Cladding Hulls from Commercial Reprocessing, NAGRA technical report 92-13, 1992.
• [7] T. S. Rudisill, ”Decontamination of Zircaloy cladding hulls from spent fuel”, J. Nucl. Mater. 285, 193 (2009).
• [8] M. K. Jeon, C. H. Lee, C. J. Park, K. H. Kang, G. I. Park, Effect of Burn-up on the radioactivation behavior of cladding materials, KAERI/TR-5100, 2013.
• [9] G. I. Park, K. K. Kim, D. Y. Lee, J. W. Lee, J. J. Park, K. C. Song, Global 2009, Paris (2009).
• [10] G. I. Park, K. H. Cho, J. W. Lee, J. J. Park, K. C. Song, ANS spring meeting, Anaheim, California (2008).
• [11] http://www.oecd-nea.org/rwm/profiles/Korea_report_web.pdf.
• [12] M. J. Bell, ORIGEN-The ORNL Isotope Generation and Depletion Code, ORNL-TM4397, 1973.
• [13] International Atomic Energy Agency, Management of cladding hulls and fuel hardware, Tech. Report Series No. 258, Vienna, 1985.

Uwagi

PL

Opracowanie ze środków MNiSW w ramach umowy 812/P-DUN/2016 na działalność upowszechniającą naukę.