PACKAGE DESIGN FOR SPENT FUEL USED FOR REACTIVITY MEASUREMENT

Year

1998

Author(s)

H.Y. Kang - Korea Atomic Energy Research Institute (KAERI)

J.O. Kim - Korea Atomic Energy Research Institute (KAERI)

Y.G. Lee - Korea Atomic Energy Research Institute (KAERI)

H.R. Cha - Korea Atomic Energy Research Institute (KAERI)

H. D. Kim - Korea Atomic Energy Research Institute (KAERI)

J.S. Hong - Korea Atomic Energy Research Institute (KAERI)

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Abstract

1be multipurpose RM -1 package has been developed to transport spent fuel rod-cuts and to measure the fissile contents and radioactive poisons of spent fuel rods. The package has been designed to handle a small amount of decay heat and to shield intensive neutron and ganuna-rays. Thermal analysis of the RM-1 package was carried out under normal heat conditions. 1be shielding analysis was done to minimize the RM -1 package weight while maintaining an overall shielci4lg effectiveness. The maximum temperatures on the surface of the fuel rod-cuts is approximately 50 t. A calculation of gamma-ray and neutron dose rates on the package surface and 2 m from the surface has been carried out It is revealed that the total dose rates under normal conditions meet the design limits specified by the domestic and IAEA package standards[IAEA, 1985].