Results 41 to 50 of about 2,496 (228)
Nuclear Engineering and Technology, 2022 Mesh and turbulence model sensitivity analyses have been performed on computational fluid dynamics simulations executed with Hydra and ANSYS Fluent for a single CANadian Deuterium Uranium (CANDU) 37M nuclear fuel bundle placed within a standard pressure ...
Z. Lu, M.H.A. Piro, M.A. Christon
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Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.Water scarcity poses a mounting constraint on Ghana’s socioeconomic development, intensified by climate‐driven hydrological variability, rapid urbanization, and industrial expansion. This study presents a Ghana‐specific techno‐economic and policy‐integrated assessment of nuclear‐powered seawater desalination, moving beyond generic applications of ...
Felix Ameyaw +3 more
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Energy Science &Engineering, Volume 13, Issue 12, Page 5810-5820, December 2025.ABSTRACT Radioactive effluents discharged by nuclear power plants (NPPs) are classified into two categories: gas and liquid effluents, based on their source and discharge pathways. During the operation of these facilities, both types of effluents are released into the environment.
Hwapyoung Kim +2 more
wiley +1 more source
A New Fuel Design for Two Different HW Type Reactors
Science and Technology of Nuclear Installations, 2011 A new fuel element (called CARA) designed for two different heavy water reactors (HWRs) is presented. CARA could match fuel requirements of both (one CANDU and one unique Siemens's design) Argentine HW reactors. It keeps the heavier fuel mass density and
Daniel O. Brasnarof +3 more
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Nuclear Engineering and Technology, 2017 In any reactor physics analysis, the instantaneous power distribution in the core can be calculated when the actual bundle-wise burnup distribution is known.
Doddy Kastanya
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Journal of Field Robotics, Volume 42, Issue 4, Page 1080-1102, June 2025.ABSTRACT The steam generator plays a crucial role as a safety component and protective barrier in nuclear power plants. Regular inspection and repair of heat transfer tubes, which operate in high‐temperature, high‐pressure, corrosive, and abrasive environments for extended periods, are essential.
Zhaojin Liu +8 more
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Nuclear Decommissioning and Sustainable Environment: Insights on Decontamination Processes
Advanced Energy and Sustainability Research, Volume 6, Issue 1, January 2025.The sequence of nuclear decommissioning and its role in promoting a sustainable environment are elucidated. Insights on strategy of nuclear decontamination technologies are highlighted, and techniques for radioactive waste treatment are discussed.
Miguta Faustine Ngulimi +4 more
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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
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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
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
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