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- W1567832211 abstract "Final design has been completed for a 1 gpm sodium sampling loop which will withdraw a continuous stream containing failed fuel in solution from the primary circuit of the Sodium Loop Safety Facility. Breeder reactor fuels are tested to destruction in the primary loop when inserted into the Engineering Test Reactor at INEL. Provisions for draining contaminated sodium to the primary loop permits a disconnect of the sampling loop after each test. The sampling loop will contain a delayed neutron monitor located remotely from the test fuels being irradiated; transit time will be 12s at rated flow. Fission products carried in sodium solution will emit delayed neutrons primarily of groups 2 and 3 (T/sub 1/2/ = 22s and 6s) in the monitor and provide a delivered efficiency of 7% for all delayed groups." @default.
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- W1567832211 date "1978-01-01" @default.
- W1567832211 modified "2023-09-27" @default.
- W1567832211 title "SLSF delayed neutron detection with the on-line sodium sampling system. [LMFBR]" @default.
- W1567832211 hasPublicationYear "1978" @default.
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