Abstract
In order to elucidate the behaviour of radioactive corrosion products (CPs) in sodium cooling systems of fast reactor the radioactive deposition and distribution within the primary system have been measured and evaluated using a model for CP transport at JOYO, the Japanese experimental fast reactor. The main purpose of the studies has been to try and establish the calculational model for predicting the release and deposition and distribution of CPs in fast reactor sodium cooling systems. This paper reports the findings from these measurements and evaluations, and highlight the feature in CP transport behaviour which have to be taken into consideration to update the model.
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References
K. Iizawa, S. Suzuki, M. Tamura, S. Seki, T. Hikichi, Proc. Specialists’ Meeting on Fission and Corrosion Products Behaviour in Primary Circuits of LMFBRs, Karlsruhe, KfK 4279 IWGFR/64 (1987) p.227.
K. Iizawa, T. Kikuchi, I. Nihei, J. Horie, ibid., p. 191.
M.V. Polley, G. Skyrme, J. Nucl. Mater., 75 (1978) 226.
W.L. Kuhn, USAEC Report HEDL-TME 76-10, September 1977.
S. Suzuki, K. Iizawa, N. Ohtani, T. Kobayashi, J. Horie, H. Handa, Proc.Topical Conference on Theory and Practices Radiation Protection and Shielding, Knoxville, Tennessee, 1987.
N. Sekiguchi, K. Iizawa, H. Atsumo, Proc. Specialists’ Meeting on Fission and Corrosion Product Behaviour in Primary Circuits of LMFBRs, Dimitrovgrad (1965) p. 82.
W. Brehm, ibid. (1975) p. 186.
N. Yokota, S. Shimoyashiki, J. Japan Inst. Metals, 53, No.2 (1989) 175.
W.F. Brehm, R.P. Colburn, H.P. Maffei, W.P. Stinson, W.L. Bunch, R.A. Bechtold, Proc. Specialists’ Meeting on Fission and Corrosion Products Behaviour in Primary Circuits of LMFBRs, Karlsruhe, KfK 4279, IWGFR/64 (1987) p. 75.
N. Yokota, J. Japan Inst. Metals, 55, No.2 (1991) 229.
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© 1995 Springer Science+Business Media New York
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Iizawa, K., Chatani, K., Ito, K., Suzuki, S., Akutsu, M., Kinjo, K. (1995). Transport of Radioactive Corrosion Products in Primary Systems of a Sodium Cooled Fast Reactor. In: Borgstedt, H.U., Frees, G. (eds) Liquid Metal Systems. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-1977-5_2
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DOI: https://doi.org/10.1007/978-1-4615-1977-5_2
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