Results 11 to 20 of about 27,183 (256)
Evaluation of fast fission factor in a typical pool type research reactor [PDF]
Journal of Nuclear Research and Applications, 2022 One of the important factors of a nuclear reactor core is the fast fission factor. This paper calculates this parameter based on space and energy-dependent method using the PTRAC card of MCNPX code. Tehran research reactor (TRR) is taken as a case study,
M. Arkani, S. Khakshournia
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Physics-basis simulation of bubble pinch-off
Mechanical Engineering Journal, 2016 In the last two decades, CFD codes have been widely used for the design studies of NPPs. Recently high-precision simulation models have been developed to evaluate complicated phenomena, e.g. fuel melting in severe accident.
Kei ITO +3 more
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EPJ Web of Conferences, 2017 The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing ESNII for Horizon 2020. ESNII stands for the European Industrial Initiative on Nuclear Energy, created by the European Commission in 2010 to promote the ...
Nuria García-Herranz +5 more
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NUMERICAL ANALYSIS OF THERMAL STRATIFICATION IN THE UPPER PLENUM OF THE MONJU FAST REACTOR
Nuclear Engineering and Technology, 2013 A numerical analysis of thermal stratification in the upper plenum of the MONJU fast breeder reactor was performed. Calculations were performed for a 1/6 simplified model of the MONJU reactor using the commercial code, CFX-13.
SEOK-KI CHOI +3 more
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Mechanical Engineering Journal, 2014 Studies on the self-leveling behavior of debris bed are crucial in the assessment of core disruptive accident (CDA) that could occur in sodium-cooled fast reactors (SFR).
Songbai CHENG +10 more
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On the Development of a Counter-flow Mixing Reactor for Fast Hydrothermal Liquefaction
Chemical Engineering Transactions, 2022 A laboratory-scale continuous tubular flow reactor system has been developed for fast HTL (hydrothermal liquefaction) of lignin, adopting the nozzle reactor concept with a counter-flow mixing design.
Arturs Curakovs, Khanh-Quang Tran
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Nuclear Engineering and Technology, 2019 This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor.
Jin Gwan Son +4 more
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Energies, 2020 In the safety analysis of sodium-cooled fast reactors, numerical simulations of various thermal-hydraulic phenomena with multicomponent and multiphase flows in core disruptive accidents (CDAs) are regarded as particularly difficult.
Md Abdur Rob Sheikh +6 more
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Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
Mechanical Engineering Journal, 2017 Under the cooperative effort of the Civil Nuclear Energy R&D Working Group within the framework of the U.S.-Japan bilateral, Argonne National Laboratory (ANL) and Japan Atomic Energy Agency (JAEA) have been performing benchmark study using the Japan ...
Kazuya OHGAMA +4 more
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Nihon Kikai Gakkai ronbunshu, 2020 The self-actuated shutdown system (SASS) is a reactor shutdown system that is able to achieve passively de-tach the absorber rod based on the coolant temperature rise under the any type of abnormal conditions and then the absorber rods will be inserted ...
Jungo KATO +4 more
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