Results 41 to 50 of about 211 (130)
Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors
EPJ Nuclear Sciences & Technologies, 2016 This paper discusses concepts for three-component fuel bundles containing plutonium, uranium and thorium for use in pressurised heavy water reactors, and cases for and against implementation of such a nuclear energy system in the United Kingdom.
Peel Ross +3 more
doaj +1 more source
Development and Verification of Activated Source Term Library Based on ENDF/B‐VIII.0
International Journal of Energy Research, Volume 2025, Issue 1, 2025.Developed by the Oak Ridge National Laboratory (ORNL) in the United States, the ORIGEN code for computing irradiation and decay processes is one of the most widely used point depletion programs. However, the nuclear data that accompanies it, crucial for its application, has been measured and evaluated a long time ago.
Xirui Zhang +6 more
wiley +1 more source
Recycling option search for a 600-MWe sodium-cooled transmutation fast reactor
Nuclear Engineering and Technology, 2015 Four recycling scenarios involving pyroprocessing of spent fuel (SF) have been investigated for a 600-MWe transmutation sodium-cooled fast reactor (SFR), KALIMER.
Yong Kyo Lee, Myung Hyun Kim
doaj +1 more source
Analysis of carbon‐14 discharges from Korean nuclear power plants
Energy Science &Engineering, Volume 12, Issue 9, Page 3576-3588, September 2024.Comparison of radioactive effluent discharges from Korean nuclear power plants before and after carbon‐14 discharge monitoring in Korean pressurized water reactors. Abstract The routine practice accompanying the operation of nuclear facilities involves the discharge of radioactive effluents from nuclear power plants (NPPs). Regulation of this discharge
Hwapyoung Kim +6 more
wiley +1 more source
Science and Technology of Nuclear Installations, 2018 The Canadian Supercritical Water-cooled Reactor (SCWR), a GEN IV reactor design, is a hybrid design of the well-established CANDU™ and Boiling Water Reactor with water above its thermodynamic critical point.
Frederic Salaun, David R. Novog
doaj +1 more source
A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters
Nuclear Engineering and Technology, 2016 Important safety parameters such as the fuel temperature coefficient (FTC) and the power coefficient of reactivity (PCR) of the CANada Deuterium Uranium (CANDU-6) reactor have been evaluated using the Monte Carlo method.
Yonghee Kim, Donny Hartanto, Woosong Kim
doaj +1 more source
Critical heat flux in a CANDU end shield – Influence of shielding ball diameter
Nuclear Engineering and Technology, 2022 Experiments were performed to measure the critical heat flux (CHF) on a vertical surface abutting a coarse packed bed of spherical particles. This geometry is representative of a CANDU reactor calandria tubesheet facing the end shield cavity during the ...
Justin Spencer
doaj +1 more source
Materials and Corrosion, Volume 75, Issue 4, Page 529-542, April 2024.The simulated E–H diagrams of nickel could be used to predict the corrosion of steam generator tubes of Canadian Deuterium Uranium reactors. Abstract Nuclear power plant steam generator (SG) tubes contain nickel as the main alloying element and there is concern about their corrosion.
Mohammad Amin Razmjoo Khollari +2 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.Based on research into the diagnosis methods for fuel failures in pressurized water reactor nuclear power plants and an analysis of existing problems, this paper proposes an enhanced fuel failure diagnosis method, addressing three key improvements: identification of the occurrence of fuel failure, diagnosis of the number of failed fuel rods, and the ...
Weifeng Lyu +5 more
wiley +1 more source
International Journal of Energy Research, Volume 2024, Issue 1, 2024.After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri +4 more
wiley +1 more source