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Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant [PDF]

open access: yesNuclear 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   +4 more sources

EVALUATION OF THE APPLICABLE REACTIVITY RANGE OF A REACTIVITY COMPUTER FOR A CANDU-6 REACTOR [PDF]

open access: yesNuclear 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   +3 more sources

Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis [PDF]

open access: yesScience 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   +5 more sources

Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method

open access: yesNuclear Engineering and Technology, 2021
KHNP recently has obtained the approval for the commercialization of the modified 37-element (or 37 M) fuel bundle and now is loading the 37 M fuel bundles in CANDU-6 reactors in KOREA. One of the main issues for approval was the burnup limit.
Eun-ki Lee
doaj   +3 more sources

Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response

open access: yesScience and Technology of Nuclear Installations, 2022
The use of the USNRC codes TRACE and PARCS has been considered for the coupled safety analysis of CANDU reactors. A key element of CANDU simulations is the interactions between thermal-hydraulic and physic phenomena with the CANDU reactor regulating ...
Simon Younan, David R. Novog
doaj   +2 more sources

Canis STR‐Seq: A Universal Approach for Non‐Invasive Genetic Monitoring of Wolves and Coyotes [PDF]

open access: yesEcology and Evolution, Volume 16, Issue 3, March 2026.
We present a new, universal microsatellite genotype‐by‐sequencing assay for Canis species that allows for unambiguous allele calls, flags homoplasy for more accurate assignment tests, and improves genotyping output from low‐template DNA. We suggest, as others have done previously, that microsatellites are still effective, affordable, and sometimes ...
Emily Walker   +3 more
wiley   +2 more sources

Unsteady Simulation of a Full-Scale CANDU-6 Moderator with OpenFOAM [PDF]

open access: yesEnergies, 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
doaj   +2 more sources

THE IMPACT OF POWER COEFFICIENT OF REACTIVITY ON CANDU 6 REACTORS

open access: yesNuclear 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
doaj   +2 more sources

Neutronic evaluation of CANDU-6 core using reprocessed fuels

open access: yesBrazilian 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 study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

open access: yesNuclear 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 ...
Jinsen Xie, Nianbiao Deng, Wenjie Zeng
exaly   +3 more sources

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