K Reactor: HCR sleeves
Description:
Irradiation Processing Department opinions regarding HCR sleeves. It is believed that Zr-2 would be a satisfactory sleeve material providing it is limited to maximum service temperatures the order of 400 degrees C. Both Inconel and a 300 series stainless steel are believed possibilities for uncooled sleeve materials, with Inconel our preference. Beryllium, in virtue of its outstanding nuclear properties and probably satisfactory chemical and mechanical properties, warrants consideration on a pi…
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Date:
December 12, 1960
Creator:
Zima, G. E.
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department