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Rx fuel dose rates
I'm trying to find rule-of-thumb values (or actual!) for total activity and
nearby (say 1 m or 10m) dose rates for reactor fuel after
irradiation. Maybe two cases: a PWR fuel assy soon after discharge with
substantial burnup, and then 15 - 20 years later (post-decay); and some
research reactor fuel at removal and then maybe 5 years later.
I know about the 6Ci/Watt T.R. and the part II problems that have been used.
Thanks in advance,
Brian Rees
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