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- W2016367592 abstract "Applied to a homogeneous solution of uranyl nitrate or plutonium nitrate, the physical mechanisms are discussed which control the mean nuclear power of a solution reactor. The short-time averaged power during the heating-up of a nonboiling solution is related to the mean flow rate of radiolytic gas which is necessary to yield a steady-state neutron flux. If the solution is boiling a similar relation to the flow rate of vapor is derived. This relation, however, can only be applied if the superheat of the solution permits vapor bubble growth. Otherwise, the minimum power for the required superheat will be obtained instead. These power relations are combined into a quasi-steady-state model which is discussed and verified by applying it to two experiments of the CRAC solution reactor." @default.
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- W2016367592 date "1986-09-01" @default.
- W2016367592 modified "2023-09-24" @default.
- W2016367592 title "Heating-up, nucleation and boiling of a critical solution of fissile material" @default.
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- W2016367592 doi "https://doi.org/10.1016/0301-9322(86)90050-9" @default.
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