Results 11 to 20 of about 9,551,406 (202)
CANDU-6 fuel optimization for advanced cycles [PDF]
AbstractWe implement a selection process based on DRAGON and DONJON simulations to identify interesting thorium fuel cycles driven by low-enriched uranium or DUPIC dioxide fuels for CANDU-6 reactors. We also develop a fuel management optimization method based on the physics of discrete on-power refueling and the time-average approach to maximize the ...
St-Aubin, Emmanuel, Marleau, Guy
openaire +2 more sources
CANDU-6 operation simulations using accident tolerant cladding candidates [PDF]
Abstract The 3D DRAGON-DONJON capabilities are exploited to simulate CANDU-6 (Canada Deuterium Uranium) core follow-up with alternate cladding materials. Aluminium-based alloys (FeCrAl and APMT), nickel-based alloys (304SS and 310SS) and silicon carbide (SiC) are compared with Zircaloy-II.
A. Naceur, G. Marleau
openaire +3 more sources
Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank [PDF]
In order to simulate the CANDU-6 moderator circulation phenomena during steady state operating and accident conditions, a scaled-down moderator test facility has been constructed at Korea Atomic Energy Institute (KAERI).
Hyoung Tae Kim +3 more
doaj +2 more sources
Effect of DUPIC Cycle on CANDU Reactor Safety Parameters [PDF]
Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (CANDU) reactors (DUPIC) cycle is still under investigation, DUPIC cycle is a promising method for uranium utilization improvement, for reduction of high ...
Nader M.A. Mohamed, Alya Badawi
doaj +2 more sources
Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors
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
This work investigates the possibility of getting rid of the accumulated plutonium around the world by mixing it with fertile materials and using it as a nuclear fuel for CANDU-6.
Ahmed Abdelghafar Galahom +1 more
exaly +3 more sources
Measurement of Velocity and Temperature Profiles in the Scaled-Down CANDU-6 Moderator Tank [PDF]
We are planning to construct a scaled-down moderator test facility to simulate the CANDU-6 moderator circulation phenomena during steady state operation and accident conditions at the Korea Atomic Energy Research Institute. In the present work a preliminary experiment using a 1/40 scaled-down moderator tank has been performed to identify the potential ...
Hyoung Tae Kim +5 more
openaire +2 more sources
AN ASSESSMENT OF THE SPATIAL VARIATION OF ISOTOPIC RATIOS IN A CANDU REACTOR FOR NUCLEAR TREATY MONITORING [PDF]
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
Uncertainties impact on the major FOMs for severe accidents in CANDU 6 nuclear power plant
In the nuclear safety studies, a new trend refers to the evaluation of uncertainties as a mandatory component of best-estimate safety analysis which is a modern and technically consistent approach being known as BEPU (Best Estimate Plus Uncertainty).The ...
R.M. Nistor-Vlad, D. Dupleac, G.L. Pavel
doaj +1 more source
Abstract Introduction Juvenile idiopathic arthritis (JIA) is the most common rheumatic disease in children and causes short‐ and long‐term disability. Optimal management requires pharmacologic and non‐pharmacologic interventions. Few studies have explored the youth and family experience of the management of JIA.
G. R. Currie +9 more
wiley +1 more source

