Abstract
For shipping spent fuels of very high burnup, the normal procedure is to place the fuels of highest burnup in the center of cask, and to surround them with those of lower burnup. The actual arrangement of these fuels within the cask is currently determined individually at the time of loading, based on experience.The present paper proposes a simple method for quantitatively evaluating the effect brought on the radiation dose rate at cask surface by differences in the arrangement of spent fuel inside the cask. The proposed method is based on a concept embodying “sensitivity to change in radia-tion source strength shown by the radiation dose at cask surface”. This concept permits quick and reliable evaluation of an arrangement of spent fuels in a cask. The concept is formulated by means of a quantity termed sensitivity coefficient of radiation dose rate, which coefficient can be easily calculated.The present method provides a means of finding an ideal array for loading spent fuels in several -including high- burnup states, once the upper limits of fuel burnup and radiation dose rate at cask surface are given.The validity of the present method is verified by a trial application to analysis of the measured radiation dose rate distributions around an actual shipping cask.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
More From: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.