摘要 :
Power and flux tracking in nuclear reactor cores are normally done using diffusion codes. These codes take into account geometric characteristics, compositions. Operative conditions And eventually thermohydraulic feed backs. Howev...
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Power and flux tracking in nuclear reactor cores are normally done using diffusion codes. These codes take into account geometric characteristics, compositions. Operative conditions And eventually thermohydraulic feed backs. However, due to operating requirements, in some Cases these reactor are instrumented with in-core neutronic flux detectors. This information is Usually used in order to verify instantaneous calculations, but it can also be used to fit the the- Oretical model and then to produce an improved solution.
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