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Surplus weapons plutonium: Technologies for pit disassembly/conversion and MOX fuel fabrication
Author(s) -
J.W. Toevs
Publication year - 1997
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/573275
Subject(s) - mox fuel , plutonium , fabrication , waste management , oxide , radioactive waste , nuclear weapon , environmental science , nuclear engineering , radiochemistry , materials science , chemistry , engineering , metallurgy , physics , nuclear physics , medicine , alternative medicine , pathology
This paper will provide a description of the technologies involved in the disposition of plutonium from surplus nuclear weapon components (pits), based on pit disassembly and conversion and on fabrication of mixed oxide (MOX) fuel for disposition through irradiation in nuclear reactors. The MOX/Reactor option is the baseline disposition plan for both the US and russian for plutonium from pits and other clean plutonium metal and oxide. In the US, impure plutonium in various forms will be converted to oxide and immobilized in glass or ceramic, surrounded by vitrified high level waste to provide a radiation barrier. A similar fate is expected for impure material in Russia as well. The immobilization technologies will not be discussed. Following technical descriptions, a discussion of options for monitoring the plutonium during these processes will be provided

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