Results 21 to 30 of about 272 (168)
Uranium Recovery from Phosphates for Self‐Sufficient Nuclear Power in the Eastern Mediterranean
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 Production of phosphate fertilizers (PF), without uranium recovery, amounts to dispersing uranium compounds on agricultural fields. These compounds are naturally hidden in phosphate rock deposits prior to processing. Such a dispersion is a cumulative environmental damage, that may become rather catastrophic in few hundred years, under the current rates
Nassar H. S. Haidar, Guglielmo Lomonaco
wiley +1 more source
Effect of multiple-failure events on accident management strategy for CANDU-6 reactors
Nuclear Engineering and Technology, 2021 Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failures should be considered more seriously rather than single failure in the licensing bases and safety cases because attempts to take accident management ...
Seon Oh YU, Manwoong KIM
doaj +1 more source
CANDU-6 fuel optimization for advanced cycles
Nuclear Engineering and Design, 2015 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 +1 more source
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
doaj +1 more source
Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis
Nuclear Engineering and Technology, 2017 This study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6 and Advanced Canada Deuterium Uranium Reactor-700 (ACR-700) fuel lattices using a Monte Carlo code.
Jinsu Park +4 more
doaj +1 more source
Numerical assessment of LOCA experiments of RD-14M using MARS-KS code
International Journal of Advanced Nuclear Reactor Design and Technology, 2020 The code assessment on the design basis events has been of fundamental importance to the safety analyses of the nuclear power plants. When a system analysis code is released to the new version by improving the existing models and correcting the found ...
Seon Oh Yu, Min Ki Cho, Kyung Lok Baek
doaj +1 more source
BACKUP AND ULTIMATE HEAT SINKS IN CANDU REACTORS FOR PROLONGED SBO ACCIDENTS
Nuclear Engineering and Technology, 2013 In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage would begin with the depletion of the liquid moderator, exposing the top row of internally-voided fuel channels to steam cooling conditions on the inside and ...
T. NITHEANANDAN, M.J. BROWN
doaj +1 more source
Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank
Science and Technology of Nuclear Installations, 2015 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 +1 more source
SAFETY ANALYSIS METHODOLOGY FOR AGED CANDU® 6 NUCLEAR REACTORS
Nuclear Engineering and Technology, 2013 This paper deals with the Safety Analysis for CANDU® 6 nuclear reactors as affected by main Heat Transport System (HTS) aging. Operational and aging related changes of the HTS throughout its lifetime may lead to restrictions in certain safety system ...
WOLFGANG HARTMANN, JONG YEOB JUNG
doaj +1 more source
Nuclear Engineering and TechnologyThis 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.
A. Abdelghafar Galahom +2 more
doaj +1 more source