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Special Section Papers

Effects of Filtered Containment Venting on Fission Product Releases During CANDU Reactor Severe Accidents

[+] Author and Article Information
A. C. Morreale

Canadian Nuclear Laboratories,
286 Plant Road,
Chalk River, ON K0J 1J0, Canada
e-mail: Andrew.Morreale@cnl.ca

L. S. Lebel

Canadian Nuclear Laboratories,
286 Plant Road,
Chalk River, ON K0J 1J0, Canada
e-mail: Luke.Lebel@cnl.ca

M. J. Brown

Canadian Nuclear Laboratories,
286 Plant Road,
Chalk River, ON K0J 1J0, Canada
e-mail: Morgan.Brown@cnl.ca

1Corresponding author.

Manuscript received July 6, 2016; final manuscript received December 6, 2016; published online March 1, 2017. Assoc. Editor: Srikumar Banerjee.

ASME J of Nuclear Rad Sci 3(2), 020907 (Mar 01, 2017) (14 pages) Paper No: NERS-16-1064; doi: 10.1115/1.4035434 History: Received July 06, 2016; Revised December 06, 2016

Severe 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.

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References

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Figures

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Fig. 1

MAAP–CANDU containment nodalization for CANDU 6

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Fig. 2

Schematic of the CANDU 6 reactor core design [9]

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Fig. 3

Station blackout containment pressure transient for no venting and FCV cases

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Fig. 4

Station blackout containment outflows for no venting (failed containment + diffuse leakage flows) and FCV (filtered venting + diffuse leakage flows) cases

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Fig. 5

Station blackout containment diffuse leakage outflows for no venting and FCV cases

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Fig. 6

Cumulative activity released (by element) for SBO no venting case

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Fig. 7

Cumulative activity released (by element) for SBO FCV case

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Fig. 8

LLOCA containment pressure transient for no venting and FCV cases

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Fig. 9

LLOCA containment outflows for no-venting (failed containment + diffuse leakage flows) and FCV (filtered venting + diffuse leakage flows) cases

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Fig. 10

LLOCA containment diffuse leakage outflows for no-venting and FCV cases

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Fig. 11

Cumulative activity released (by element) for LLOCA no-venting case

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Fig. 12

Cumulative activity released (by element) for LLOCA FCV case

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Fig. 13

Cumulative activity (I and Sr) released for SBO and LLOCA scenarios

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Fig. 14

Cumulative activity (Cs and Te) released for SBO and LLOCA scenarios

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