Results 11 to 20 of about 261 (180)
Science 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
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Nuclear Engineering and Technology, 2014 In terms of safety and the efficient management of spent fuel storage, detecting failed fuel is one of the most important tasks in a CANada Deuterium Uranium (CANDU) reactor operation.
Jonghyeon Lee
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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 ...
Jinsen Xie +2 more
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Effect of DUPIC Cycle on CANDU Reactor Safety Parameters
Nuclear Engineering and Technology, 2016 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
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Science and Technology of Nuclear Installations, 2023 In CANDU reactors, shim operation is used when the online refuelling capability becomes temporarily unavailable. Adjuster rods, normally in-core to provide flux flattening, are withdrawn in sequence to provide additional reactivity as the fuel is ...
Simon Younan, David R. Novog
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Science and Technology of Nuclear Installations, 2019 This study presents the time-dependent analyses of transmutations of long-lived fission products (LLFPs) and medium-lived fission products (MLFPs) occurring in thermal reactors in a conceptual helium gas-cooled accelerator-driven system (ADS).
Alper Buğra Arslan +3 more
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Auto Sizing of CANDU Nuclear Reactor Fuel Channel Flaws from UT Scans [PDF]
Sensors, 2023 Issam Hammad, Ryan Simpson
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Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor [PDF]
Nuclear 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
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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
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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
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