Results 11 to 20 of about 848 (238)
Analysis of Loss-of-Coolant Accidents in the NBSR [PDF]
, 2014 This report documents calculations of the fuel cladding temperature during loss-of-coolant accidents in the NBSR. The probability of a pipe failure is small and procedures exist to minimize the loss of water and assure emergency cooling water flows into the reactor core during such an event.
L. Cheng, D. Diamond
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Analysis of mass transfer processes in a reactor during a loss-of-coolant accident [PDF]
Nuclear Energy and Technology, 2018 The purpose of the work was to optimize the parameters of the spillage system equipped with a gas pressure hydroaccumulator for a ship pressurized water reactor in a loss-of-coolant accident.
Aleksey Kulikov +2 more
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Core Reactivity Analysis during Fuel Draining Process in the Molten Salt Fast Reactor
JIF (Jurnal Ilmu Fisika), 2022 A study of the core criticality during the draining process of liquid fuel salt on Molten Salt Fast Reactor (MSFR) was done. Two accident scenario that causes the draining process were loss of freeze valve coolant and loss of secondary coolant.
Puti Berkah Azurah +2 more
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Nuclear Engineering and Technology, 2021 To establish the exclusive role of hydrogen on burst behaviour of Zircaloy-4 during loss-of-coolant accident transients, an extensive single-rod burst tests were conducted on both unirradiated as-received and hydrogenated Zircaloy-4 cladding tubes at ...
Siddharth Suman
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Quenching Experiments with CrAl-coated Zircaloy Cladding in Reflooding Water Flows
Energies, 2021 A quenching experiment is performed to investigate the heat transfer characteristics and cooling performance of CrAl-coated Zircaloy (Zr) cladding in a water flow. The CrAl-coated Zr cladding is one of the accident tolerant fuels for light water reactors.
Wang Kee In, Kwan Geun Lee
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ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION
Journal of Energy : Energija, 2022 The Spent Fuel Pool (SFP) in a nuclear power plant is a robust structure designed to withstand large seismic loads. After the terrorist attacks on September 11 and the accident in the Fukushima nuclear power plant, special attention was focused on safety assessments and taking measures to mitigate possible accidents related to the spent fuel pool. This
ĐAKOVIĆ, JOSIP, GRGIĆ, DAVOR
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CSPACE for a simulation of core damage progression during severe accidents
Nuclear Engineering and Technology, 2021 CSPACE (Core meltdown, Safety and Performance Analysis CodE for nuclear power plants) for a simulation of severe accident progression in a Pressurized Water Reactor (PWR) is developed by coupling of verified system thermal hydraulic code of SPACE (Safety
JinHo Song +6 more
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Frontiers in Energy Research, 2021 This article simulates the multiphysics coolant thermohydraulic conditions and fuel performance of a pressurized water reactor (PWR) during a loss-of-coolant accident (LOCA).
Meng Yu +3 more
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Loading pattern optimization of a PWR reactor fuel assemblies using PESA-II algorithm by considering neutronic and thermal-hydraulic parameters [PDF]
مجله علوم و فنون هستهای, 2020 The multi-objective optimization methods are widely used in various areas of science and engineering. In this paper, a multi-objective optimization algorithm has been used to design the optimal placement of fuel assemblies in the KWU reactor with the ...
R. Gharari, B. Salmasian, O. Safarzadeh
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Nuclear Engineering and Technology, 2018 An experiment was performed using the large-scale test facility (LSTF), which simulated a 1% vessel upper head small-break loss-of-coolant accident with an accident management (AM) measure under an assumption of total-failure of high-pressure injection ...
Takeshi Takeda
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