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ANALYSES OF A SHIPPING CASK (MODEL FSV-2) FOR TRANSPORTATION OF MIXED FISSION PRODUCTS.
Author(s) -
H. Reeser
Publication year - 1972
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4637107
Subject(s) - rod , spent nuclear fuel , nuclear engineering , fabrication , core (optical fiber) , thorium fuel cycle , cask , materials science , uranium dioxide , nuclear fuel , fission products , spent fuel pool , environmental science , uranium , waste management , thorium , engineering , composite material , metallurgy , medicine , alternative medicine , pathology

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