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.

References

References
1.
Jacquemain
,
D.
,
Guentay
,
S.
,
Basu
,
S.
,
Sonnenkalb
,
M.
,
Lebel
,
L.
,
Allelein
,
H. J.
,
Liebana-Martinez
,
B.
,
Eckardt
,
B.
, and
Ammirabile
,
L.
,
2014
, “
Status Report on Filtered Containment Venting
,” Organization for Economic Cooperation and Development—Nuclear Energy Agency,
Report No. NEA/CSNI/R(2014)7
.
2.
CNSC
,
2015
, “
Study of Consequences of a Hypothetical Severe Nuclear Accident and Effectiveness of Mitigation Measures
,”
Canadian Nuclear Safety Commission
, Ottawa, ON, Canada.
3.
Chao
,
J. J.
,
Singh
,
A.
,
Henry
,
R.
,
Plys
,
M.
, and
Paik
,
C. Y.
,
1996
, “
The MAAP Code: What is It, What Has It Accomplished, and How Can It Be Used in the Future?
,”
Trans. Am. Nucl. Soc.
,
74
, pp.
358
359
.
4.
Mathew
,
P. M.
,
Petoukhov
,
S. M.
, and
Brown
,
M. J.
,
2007
, “
An Overview of MAAP4-CANDU Code
,”
28th Annual Conference of the Canadian Nuclear Society
, Saint John, New Brunswick, Canada, June 3–6.
5.
Silberberg
,
M.
,
Mitchell
,
J. A.
,
Meyer
,
R. O.
, and
Ryder
,
C. P.
,
1986
, “
Reassessment of the Technical Bases for Estimating Source Terms
,” United States Nuclear Regulatory Commission, Rockville, MD,
Report No. NUREG-0956
.
6.
Kelly
,
J. L.
,
Reynolds
,
A. B.
, and
McGown
,
M. E.
,
1984
, “
Temperature Dependence of Fission Product Release Rates
,”
Nucl. Sci. Eng.
,
88
(
2
), pp.
184
191
.
7.
Brown
,
M. J.
, and
Bailey
,
D. G.
,
2016
, “
Fission Product Releases From a PHWR Terminal Debris Bed
,”
CNL Nucl. Rev.
,
5
(
1
), pp.
95
105
.
8.
Song
,
Y. W.
,
Jeong
,
H. S.
,
Park
,
S. Y.
,
Kim
,
D. H.
, and
Song
,
J. H.
,
2013
, “
Overview of Containment Filtered Vent Under Severe Accident Conditions at Wolsong NPP Unit 1
,”
Nucl. Eng. Technol.
,
45
(
5
), pp.
597
604
.
9.
Candu Energy
,
2012
, “
EC6: Enhanced CANDU 6 Technical Summary
,”
Candu Energy
,
Mississauga, ON, Canada
.
You do not currently have access to this content.