Results 131 to 140 of about 272 (168)
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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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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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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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CANDU-6 accident analysis: Large breaks
2020Ill ABSTRACT The large break loss of coolant accidents (LOCA) in CANDU-6 reactor are analyzed. RELAP5 computer code, which has been developed for the best estimate transient simulation of water reactor coolant system during postulated accidents, is used for LOCA calculations.
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Use of Virtual Reality Technology for CANDU 6 Reactor Fuel Channel Operation Training
2020The CANDU (CANada Deuterium Uranium) 6 nuclear reactor core consists of 380 horizontal fuel channels that hold the fuel in the reactor core and allow for the expansion of the fuel channel components. Fuel channel assembly enables the heat transfer from the nuclear fuel to heavy water coolant.
Ziqi Fan +8 more
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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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A Scaling Analysis of a CANDU-6 Moderator Tank Scaled-Down Test Facility
Volume 4: Thermal Hydraulics, 2013Several studies have been performed to derive a set of scaling criteria which were thought to be suitable for reproducing thermal-hydraulic phenomena in a scale-down CANDU moderator tank similar to that in a prototype power plant during a full power steady state condition[1,2].
Bo W. Rhee +4 more
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Maintenance Strategy for Branch Connection on the Hot Leg of Steam Generator in CANDU 6
18th International Conference on Nuclear Engineering: Volume 1, 2010A maintenance strategy to repair or modify the dissimilar weld on the branch connection of the steam generator hot leg in CANDU6 was developed. The repair method is to add a carbon steel pipe spool as a transition fitting to transfer the dissimilar weld to shop welding, and the modification method is to use the backup tap fabricated during plant ...
Liang Zhao +3 more
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CANDU 6 Accident Analysis Using RELAP/SCDAPSIM With the Integrated Uncertainty Package
Volume 9: Student Paper Competition, 2018RELAP/SCDAPSIM is a best-estimate nuclear tool designed to analyze the behaviour of reactor systems during normal and accident conditions. Three main versions of RELAP/SCDAPSIM are currently used by program members and licensed users to support a variety of activities.
Roxana-Mihaela Nistor-Vlad +5 more
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Simulation of the Internal Flows of an Inlet Diffuser Assembly for the CANDU-6 Moderator Analysis
Nuclear Technology, 2007The fluid flows going through the Canada Deuterium Uranium (CANDU) moderator inlet diffuser assembly consist of a pipe flow, a curved pipe flow, and an impinging jet. For predicting the velocity profile at the diffuser outlet faces, a computational fluid dynamics (CFD) analysis has been performed to simulate the internal flow in the diffuser assembly ...
Churl Yoon, Joo Hwan Park
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