Results 1 to 10 of about 253 (151)
Unsteady Simulation of a Full-Scale CANDU-6 Moderator with OpenFOAM [PDF]
Energies, 2019 Three-dimensional moderator flow in the calandria tank of CANDU-6 pressurized heavy water reactor (PHWR) is computed with Open Field Operation and Manipulation (OpenFOAM), an open-source computational fluid dynamics (CFD) code.
Hyoung Tae Kim +2 more
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Neutronic evaluation of CANDU-6 core using reprocessed fuels
Brazilian Journal of Radiation Sciences, 2020 The spent fuel from a PWR still contains some amount of fissile materials depending on their initial enrichment and the burnup. Thus, spent fuel from PWRs containing about 1.5% of fissile material could be used as fuel for CANDU reactors after some ...
Clarysson Alberto Mello da Silva +4 more
doaj +2 more sources
Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant [PDF]
Nuclear Technology and Radiation Protection, 2017 In recent years, extended studies are developed for investigation the effects of using nanofluids in NPP as coolant. CANDU-6 reactors have the potential to use nanofluid coolants because in these reactors, the moderator system is fully ...
Mirghaffari Reza +2 more
doaj +3 more sources
THE IMPACT OF POWER COEFFICIENT OF REACTIVITY ON CANDU 6 REACTORS
Nuclear Engineering and Technology, 2013 The combined effects of reactivity coefficients, along with other core nuclear characteristics, determine reactor core behavior in normal operation and accident conditions.
D. KASTANYA +3 more
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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
Nuclear Engineering and Technology, 2019 Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average ...
Nianbiao Deng, Wenjie Zeng
exaly +3 more sources
Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis [PDF]
Science and Technology of Nuclear Installations, 2015 The current neutronics design methodology of CANDU-PHWRs based on the two-step calculations requires determining not only homogenized two-group constants for ordinary fuel bundle lattice cells by the WIMS-AECL lattice cell code but also incremental two ...
Seung Yeol Yoo +2 more
doaj +3 more sources
EVALUATION OF THE APPLICABLE REACTIVITY RANGE OF A REACTIVITY COMPUTER FOR A CANDU-6 REACTOR
Nuclear Engineering and Technology, 2014 Recently, a CANDU digital reactivity computer system (CDRCS) to measure the worth of the liquid zone controller in a CANDU-6 was developed and successfully applied to a physics test of refurbished Wolsong Unit 1.
EUN KI LEE, DONG HWAN PARK, WHAN SOO LEE
doaj +2 more sources
Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors
Annals of Nuclear Energy, 2018 Abstract The neutronic penalty and advantages are quantified for potential accident tolerant claddings in a CANDU-6 (Canada Deuterium Uranium) reactor. Ferritic-based alloy (FeCrAl and APMT), steel-based alloy (304SS and 310SS) and silicon carbide (SiC) claddings are compared with Zircaloy-II.
G Marleau
exaly +3 more sources
Moderator Flow Simulation Around Calandria Tubes of Candu-6 Nuclear Reactors [PDF]
Engineering Applications of Computational Fluid Mechanics, 2014 AbstractCFD simulations of cross-flows along in-line and staggered tube bundles which emulate those encountered in the calandria of CANDU-6 reactors are presented. The knowledge of external wall temperature distributions around calandria tubes is a major concern during normal and off-normal operating conditions of CANDU reactors.
A Teyssedou +2 more
exaly +3 more sources
AN ASSESSMENT OF THE SPATIAL VARIATION OF ISOTOPIC RATIOS IN A CANDU REACTOR FOR NUCLEAR TREATY MONITORING [PDF]
EPJ Web of Conferences, 2021 A 3-D Quarter-Core CANDU-6 is modeled using Serpent 2 for nuclear treaty monitoring. The spatial variation of flux spectra and isotopic concentrations is analyzed to determine the potential isotopic distribution of key radionuclides from standard reactor
Burkhardt Aaron W. +2 more
doaj +1 more source