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CANDU 6 Severe Accident Prevention and Mitigation Features
Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 2012The CANDU 6 design includes features, both engineered and inherent, that act as barriers to prevent and mitigate severe accidents at progressive stages of a beyond design basis event such as that which occurred at Fukushima in March 2011. CANDU 6 has ample design margins including multiple layers of defense.
Steven Ford +4 more
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PIV measurements of the flow patterns in a CANDU-6 model
Annals of Nuclear Energy, 2016Abstract Particle image velocimetry (PIV) measurements of the flow patterns in a pressurized heavy water reactor (PHWR) were made in a 1/4 scaled-down model of the Canadian deuterium uranium (CANDU) reactor. Archimedes’ number (Ar) was introduced to evaluate the dynamic similarities between the isothermal (Ar = 0) and heating conditions.
Sunghyuk Im +3 more
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User Effect on the Thermal-Hydaulic Behavior of the CANDU 6 Reactors
2019 International Conference on ENERGY and ENVIRONMENT (CIEM), 2019During the past years, conservative assumptions compensated the uncertainties in the computer models used in the design and licensing of the nuclear power plants. The use of conservatism impacts significantly the results regarding the plant behavior and does not provide a clear picture on the plant's safety.
Roxana-Mihaela Nistor-Vlad +2 more
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Static strength analysis of CANDU-6 reactor fuel bundle
Nuclear Engineering and Design, 2000Abstract A static analysis, finite-element (FE) model was developed to simulate out-reactor fuel–string strength tests with use of the well-known, structural analysis computer code ABAQUS. The FE model takes into account the deflection of fuel elements, and stress and displacement in endplates subjected to hydraulic drag loads.
Moon-Sung Cho +3 more
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An evaluation of a general venting strategy in a CANDU 6 reactor building
Annals of Nuclear Energy, 2007Abstract If the reactor building sprays or local air coolers are not available, depressurization by reactor building venting is considered as a useful mitigation strategy for a severe accident management of the Wolsong plants. As the containment filtered vent system is not established in the Wolsong Units, the reactor building isolation system can be
See-Darl Kim +4 more
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SCDAP/RELAP5 Analysis of Progression of Severe Accident in CANDU 6 Plant
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 2009The CANDU system design has specific features which are important to severe accidents progression and require selective consideration of models, methods and techniques of severe accident evaluation. Moreover, it should be noted that the mechanistic models for severe accident in CANDU system are largely less validated and, as a consequence, the level of
Daniel Dupleac +2 more
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An evaluation of the severe accident management strategies for CANDU-6 type plants
Annals of Nuclear Energy, 2009Abstract This paper provides an evaluation of the mitigation effects for the severe accident management strategies of the Wolsong plants which are typical CANDU-6 type reactors. The evaluation includes the effect of the following six mitigation strategies: (1) injection into the primary heat transport system (PHTS), (2) injection into the calandria ...
Soo-Yong Park, Sang-Baik Kim
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Tritium: its generation and pathways to the environment at CANDU 6 generating stations
Nuclear Engineering and Design, 1996Abstract Tritium production rates and its pathways in CANDU 6 generating stations are studied in this paper. Tritium is generated primarily by the D(n, γ)T reaction in the reactor core. The major sources of tritium are moderator and coolant heavy water which are exposed to high neutron flux levels during reactor operation. A small amount of tritiated
Tae-Keun Park, Seon-Ki Kim
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Nuclear Technology, 2007
The effect of advanced resonance self-shielding models incorporated in the developmental version of the DRAGON code on estimation of reactivity coefficients of a typical CANDU-6 lattice is evaluated. The advanced self-shielding models are based on either equivalence in the dilution model or on a subgroup approach.
Ramamoorthy Karthikeyan, Alain Hébert
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The effect of advanced resonance self-shielding models incorporated in the developmental version of the DRAGON code on estimation of reactivity coefficients of a typical CANDU-6 lattice is evaluated. The advanced self-shielding models are based on either equivalence in the dilution model or on a subgroup approach.
Ramamoorthy Karthikeyan, Alain Hébert
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Development of a CFD model for the CANDU-6 moderator analysis using a coupled solver
Annals of Nuclear Energy, 2008Abstract A computational fluid dynamics (CFD) moderator analysis model by using a coupled solver has been developed for the moderator analysis of Canada deuterium uranium (CANDU) reactors. For Wolsong Units 2/3/4, a steady-state moderator circulation under operating conditions and the local moderator subcooling during a LOCA transient were evaluated ...
Churl Yoon, Joo Hwan Park
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