Richland Five-year 02 R&D Program
Publication year - 1968
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/26553
Subject(s) - radionuclide , waste management , radioactive waste , environmental science , plutonium , slurry , strontium 90 , uranium , radiochemistry , chemistry , engineering , environmental engineering , materials science , nuclear physics , physics , metallurgy
This program is directed to the production of higher weight plutonium isotopes and transplutonium isotopes from the irradiation of transuranic elements, particularly plutonium. Since production of Pu-238 from the irradiation of Np-237 and Am-241 is the subject of Mission 4, Pu-238 Program, it is excluded from this Mission. Specific products which are of prime interest are Cm-244 and plutonium containing a high concentration of either the Pu-240 isotope or the Pu-242 isotope. Because of the potential interest in Cm-244 as a heat source in the 1970`s, the main emphasis has been to provide the capability for producing this isotope. In support of this program, irradiations have been performed to obtain isotopic buildup rates, and a production and economic calculational model has been prepared for determining production methods and costs of producing Cm-244 in the Richland complex. The Richland production reactors have particular advantages in producing higher weight plutonium isotopes from the irradiation of plutonium because of a desirable neutron flux spectrum and a high heat removal capability. Specifically, the high temperature thermal neutron flux maximizes the capture-to-fission ratio of the Pu-239 and Pu-241 isotopes; the high heat removal capability provides for the large decrease in heat generation in the plutonium elements with minimum effect on reactor power levels and efficiency
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