Results 121 to 130 of about 272 (168)
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The core pressure drop characteristics in a CANDU 6 reactor
Annals of Nuclear Energy, 2013Abstract The core pressure drop characteristics in a CANDU 6 have been examined to reveal the mechanism inducing the difference in the core pressure drop among four passages. The general characteristics for the inlet header temperature and core pressure drop are deduced from the measured data of CANDU 6 NPPs.
Jun Ho Bae, Jong Yeob Jung
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Applications of ASTEC integral code on a generic CANDU 6
Nuclear Engineering and Design, 2015Abstract In case of a hypothetical severe accident in a nuclear power plant, the corium consisting of the molten reactor core and internal structures may flow onto the concrete floor of containment building. This would cause an interaction between the molten corium and the concrete (MCCI), in which the heat transfer from the hot melt to the concrete ...
Gabriela Radu, Ilie Prisecaru
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BEPU Approach in the CANDU 6 Severe Accident Analysis
2019 International Conference on ENERGY and ENVIRONMENT (CIEM), 2019The worst nuclear accident after Cernobil (in April 1986), the Fukushima Daichii accident from March 11th, 2011 has increased nuclear experts interest, all over the world, on the implementation of severe accident management measures in order to maintain the integrity of the safety barriers.
Robert Musoiu +3 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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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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Approaching Dynamic PSA Within CANDU 6 NPPs
18th International Conference on Nuclear Engineering: Volume 3, 2010The plant dynamics and the interactions of plant systems and operator with the random evolution of parameters led to the development of dynamic reliability methodologies. The present paper approaches a dynamic PSA methodology by making use of the thermal–hydraulic model of CANDU 6 reactor, implemented in RELAP5 Mod.3.3, and of IDDA code.
M. Lontos, M. Mazzini, D. Mazzini
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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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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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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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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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