
doi: 10.2172/5194568
This report documents work performed at the Idaho National Engineering Laboratory (INEL) in support of Westinghouse Hanford Company safety analyses for the N Reactor. The portion of the work reported here includes comparisons of RELAP5/MOD2-calculated data with measured plant data for: (1) a plant trip reactor transient from full power operation; and (2) a hot dump test performed prior to plant startup. These qualitative comparisons are valuable because they provide an indication of the capabilities of the RELAP5/MOD2 code to simulate operational and blowdonw transients in the N Reactor. 9 refs., 12 figs., 4 tabs.
Water Cooled Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Enriched Uranium Reactors, Production Reactors, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, 220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors, Reactor Accidents, Transients, Information, N-Reactor, Theoretical Data, Reactor Shutdown, R Codes, 22 General Studies Of Nuclear Reactors, Data, Reactor Safety, Computer Codes, 600, Shutdowns, Heat Transfer, Reactors, Numerical Data, Power Reactors, Energy Transfer, Accidents, Graphite Moderated Reactors, Lwgr Type Reactors, Safety, Plutonium Production Reactors
Water Cooled Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Enriched Uranium Reactors, Production Reactors, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, 220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors, Reactor Accidents, Transients, Information, N-Reactor, Theoretical Data, Reactor Shutdown, R Codes, 22 General Studies Of Nuclear Reactors, Data, Reactor Safety, Computer Codes, 600, Shutdowns, Heat Transfer, Reactors, Numerical Data, Power Reactors, Energy Transfer, Accidents, Graphite Moderated Reactors, Lwgr Type Reactors, Safety, Plutonium Production Reactors
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