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contributor authorMorreale, A. C.
contributor authorLebel, L. S.
contributor authorBrown, M. J.
date accessioned2017-11-25T07:18:39Z
date available2017-11-25T07:18:39Z
date copyright2017/1/3
date issued2017
identifier issn2332-8983
identifier otherners_003_02_020907.pdf
identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235302
description abstractSevere accidents are of increasing concern in the nuclear industry worldwide since the accidents at Fukushima Daiichi (March 2011). These events have significant consequences that must be mitigated to ensure public and employee safety. Filtered containment venting (FCV) systems are beneficial in this context as they would help to maintain containment integrity while also reducing radionuclide releases to the environment. This paper explores the degree to which filtered containment venting would reduce fission product releases during two Canada Deuterium Uranium (CANDU) 6 severe accident scenarios, namely a station blackout (SBO) and a large loss of coolant accident (LLOCA) (with limited emergency cooling). The effects on the progression of the severe accident and radionuclide releases to the environment are explored using the Modular Accident Analysis Program (MAAP)–CANDU integrated severe accident analysis code. The stylized filtered containment venting system model employed in this study avoids containment failure and significantly reduces radionuclide releases by 95–97% for non-noble gas fission products. Filtered containment venting is shown to be a suitable technology for the mitigation of severe accidents in CANDU, maintaining containment integrity and reducing radionuclide releases to the environment.
publisherThe American Society of Mechanical Engineers (ASME)
titleEffects of Filtered Containment Venting on Fission Product Releases During CANDU Reactor Severe Accidents
typeJournal Paper
journal volume3
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4035434
journal fristpage20907
journal lastpage020907-14
treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002
contenttypeFulltext


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