Abstract
A gas detection system (DRG) is designed in the sodium-cooled fast reactor (SFR) to limit the release of fissile material into the coolant. The system monitors a fission gas signal in the cover gas resulting from a cladding failure. We developed a general methodology to describe the entire detection process, which can be applied to arbitrary SFRs with different fuel and core designs and contribute to the conception choice and optimization for future design. We defined a corresponding equation consisting of several modules, including fission gas quantity accumulated in the fuel gas plenum, the gas leakage flux through the crack, the transportation from the fuel pin to the detector, and the detector sensitivity to different isotopes. We presented a mathematical model to determine the fission gas activity in the detector as a function of the crack size on the cladding. The methodology is applied and modeled in the PHENIX reactor for illustration purposes. With the deduced methodology, we analyzed the entire system and discussed the future design of the DRG system.
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