Results 11 to 20 of about 20,000 (260)
Thermal Hydraulic Analysis of FIRE Divertor [PDF]
Fusion Technology, 2001 The Fusion Ignition Research Experiment (FIRE) is being designed as a next step in the U.S. magnetic fusion program. The FIRE tokamak has a major radius of 2 m, a minor radius of 0.525 m, and liquid nitrogen cooled copper coils. The aim is to produce a pulse length of 20 s with a plasma current of 6.6 MA and with alpha dominated heating.
Baxi, C. B. +3 more
openaire +1 more source
Trudy Odesskogo Politehničeskogo Universiteta, 2018 At the moment, Ukraine and a number of other countries are implementing a program to extend the operation of nuclear power plants beyond the design period.
Олександр Сергійович Мазурок +1 more
doaj +5 more sources
Numerical Study of Flow and Heat Transfer Characteristics in a Simplified Dual Fluid Reactor
Energies, 2023 This study presents the design and computational fluid dynamics (CFD) analysis of a mini demonstrator for a dual fluid reactor (DFR). The DFR is a novel concept currently under investigation. The DFR is characterized by the implementation of two distinct
Hisham Elgendy, Konrad Czerski
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Assessment of RELAP5 model for the University of Massachusetts Lowell Research Reactor [PDF]
Nuclear Technology and Radiation Protection, 2006 RELAP5 is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants.
Bousbia-Salah Anis +5 more
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Thermal-hydraulic Assessment of Seven Wire-wrapped rod Bundle [PDF]
E3S Web of Conferences, 2020 Lead bismuth eutectic (LBE) is one of the most potential materials for coolant and spallation target for Accelerator Driven Systems (ADS). Thermal-hydraulic behavior of LBE in fuel assembly is a key issue for development of the systems.
Lyu Kefeng, Sheng Xuelei, Ma Xudan
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Thermal-hydraulic analysis of light water reactors under different steady-state operating conditions, Part 1: Boiling water reactor [PDF]
Nuclear Technology and Radiation Protection, 2022 The steady-state thermal-hydraulic analysis of the core of the Boiling Water Reactor (BWR/6) at nominal operating conditions is presented in this paper. The BWR/6 is produced by General Electric USA.
Hutli Ezddin, Kridan Ramadan
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Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model [PDF]
Journal of Applied and Computational Mechanics, 2017 Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the
Reza Akbari +2 more
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Thermal-Hydraulic Analysis Tasks for ANAV NPPs in Support of Plant Operation and Control
Science and Technology of Nuclear Installations, 2008 Thermal-hydraulic analysis tasks aimed at supporting plant operation and control of nuclear power plants are an important issue for the Asociación Nuclear Ascó-Vandellòs (ANAV).
F. Reventós +4 more
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Science and Technology of Nuclear Installations, 2019 COMSOL Multiphysics has been used to conduct thermal-hydraulic analysis in multiple nuclear applications. The aim of this study is to benchmark the prediction accuracy of COMSOL Multiphysics in performing thermal-hydraulic analysis of TRIGA (Training ...
Ahmed K. Alkaabi, Jeffrey C. King
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Frontiers in Energy Research, 2022 Alterations in thermal hydraulic parameters directly affect the safety of reactors. Accurately predicting the trends of key thermal hydraulic parameters under various working conditions can greatly improve reactor safety, thereby effectively preventing ...
Jinhao Yi +3 more
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