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Description
This report is a compilation of the results of reactor physics calculations to date for the currently proposed Molten Salt Reactor Experiment (MSRE) core design. Estimates have been made of the reactor characteristics using the core model and calculation methods discussed in Reactor Model and Calculation Methods; these results are presented in Table 1 and discussed in Results. Consideration is given to the problems of fission product buildup, fuel salt and Xe-135 retention by the core graphite, and distortion of the core graphite under irradiation in Long-term Reactor Behavior.
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Added Title:
Oak Ridge National Laboratory Report CF-61-4-62
Description
This report is a compilation of the results of reactor physics calculations to date for the currently proposed Molten Salt Reactor Experiment (MSRE) core design. Estimates have been made of the reactor characteristics using the core model and calculation methods discussed in Reactor Model and Calculation Methods; these results are presented in Table 1 and discussed in Results. Consideration is given to the problems of fission product buildup, fuel salt and Xe-135 retention by the core graphite, and distortion of the core graphite under irradiation in Long-term Reactor Behavior.
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