Results 1 to 10 of about 2,496 (228)

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 ...
Nianbiao Deng, Wenjie Zeng
exaly   +3 more sources

AN ASSESSMENT OF THE SPATIAL VARIATION OF ISOTOPIC RATIOS IN A CANDU REACTOR FOR NUCLEAR TREATY MONITORING [PDF]

open access: yesEPJ 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

VALIDATION OF THE POLARIS CANDU EXTENSION FOR LATTICE PHYSICS [PDF]

open access: yesEPJ Web of Conferences, 2021
Polaris is a new lattice physics package, introduced in version 6.2 of the SCALE package. It uses a method of characteristics transport solver and the embedded self-shielding method.
Younan Simon, Novog David
doaj   +1 more source

Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor [PDF]

open access: yesNuclear Technology and Radiation Protection, 2022
The study presents the analysis of the reusability of ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. The spent UO2 fuels are taken out from pressurized water reactor and CANDU spent fuels.
Durmaz Busra   +3 more
doaj   +1 more source

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   +1 more source

An empirical investigation of socio-economic impacts of agglomeration economies in major cities of Punjab, Pakistan

open access: yesCogent Economics & Finance, 2021
Agglomeration economies are the external benefits earned from clustering of industries and people in cities. The study assumes unbridled clustering of population in emerging urban agglomerations turning economies into diseconomies. This study empirically
Naghmana Ghafoor   +3 more
doaj   +1 more source

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   +1 more source

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   +1 more source

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   +1 more source

Multilevel modeling of diametral creep in pressure tubes of Korean CANDU units

open access: yesNuclear Engineering and Technology, 2021
: In this work, we applied a multilevel modeling technique to estimate the diametral creep in the pressure tubes of Korean Canada Deuterium Uranium (CANDU) units. Data accumulated from in-service inspections were used to develop the model. To confirm the
Gyeong-Geun Lee   +4 more
doaj   +1 more source

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