Potential effects of the fire protection system sprays at Browns Ferry on fission product transport [electronic resource]

The fire protection system (FPS) sprays within any nuclear plant are not intended to mitigate radioactive releases to the environment resulting from severe core-damage accidents. However, it has been shown here that during certain postulated severe accident scenarios at the Browns Ferry Nuclear Plan...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1983.
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MARC

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500 |a International meeting on light-water reactor severe accident evaluation, Cambridge, MA, USA, 28 Aug 1983. 
500 |a Niemczyk, S.J. 
520 3 |a The fire protection system (FPS) sprays within any nuclear plant are not intended to mitigate radioactive releases to the environment resulting from severe core-damage accidents. However, it has been shown here that during certain postulated severe accident scenarios at the Browns Ferry Nuclear Plant, the functioning of FPS sprays could have a significant impact on the radioactive releases. Thus the effects of those sprays need to be taken into account for realistic estimation of source terms for some accident scenarios. The effects would include direct ones such as cooling of the reactor building atmosphere and scrubbing of radioactivity from it, as well as indirect effects such as an altered likelihood of hydrogen burning and flooding of various safety-related pumps in the reactor building basement. Thus some of the impacts of the sprays would be beneficial with respect to mitigating releases to the environment but some others might not be. The effects of the FPS would be very scenario dependent with a wide range of potential effects often existing for a given accident sequence. Any generalization of the specific results presented here for Browns Ferry to other nuclear plants must be done cautiously, as it appears from a preliminary investigation that the relevant physical and operational characteristics of FPS spray systems differ widely among even otherwise apparently similar plants. Likewise the standby gas treatment systems, which substantially impact the effects of the FPS, differ significantly among plants. More work for both Mark I plants and other plants, BWRs and PWRs alike, is indicated so the potential effects of FPS spray systems during severe accidents can be at least ball-parked for more realistic accident analyses. 
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650 7 |a Power Reactors.  |2 local. 
650 7 |a Water Moderated Reactors.  |2 local. 
650 7 |a Browns Ferry-1 Reactor.  |2 local. 
650 7 |a Fission Product Release.  |2 local. 
650 7 |a Water Cooled Reactors.  |2 local. 
650 7 |a Bwr Type Reactors.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Enriched Uranium Reactors.  |2 local. 
650 7 |a Mixed Spectrum Reactors.  |2 local. 
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