Results 21 to 30 of about 848 (238)
Nuclear Engineering and Technology, 2018 An experiment was conducted for the OECD/NEA ROSA-2 Project using the large-scale test facility (LSTF), which simulated a 17% hot leg intermediate-break loss-of-coolant accident in a pressurized water reactor (PWR).
Takeshi Takeda, Iwao Ohtsu
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Journal of Nuclear Engineering, 2023 This paper presents the results obtained from numerical evaluations for the possibility of large-scale 238Pu production in the light-water VVER-1000 reactor and the reactivity effect caused by the loss-of-coolant accident in the central fuel assembly of ...
Anatoly N. Shmelev +5 more
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Hydraulic transients for loss of coolant accidents [PDF]
, 1986 This paper discusses calculations related to hydraulics in a loss of coolant reactor accident. Earlier calculations ignored the effect of emergency coolant injection. Present results show that if the ECS flow is considered, reactor coolant flow is maintained for much longer periods.
openaire +2 more sources
Temperature of JPDR Fuel at Loss-of-Coolant Accident
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1964 Calculations are made of JPDR fuel temperature at loss-of-coolant accident. At the accident, the reactor is scrammed either by a low-reactor-water-level signal or by a high-enclosure-pressure signal, and the core spray system is initiated.In analyses, a fuel rod and a clad is devided into six and two annulus sections, respectively.
TOGO, Yasumasa, YAMAZAKI, Yoshihide
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Effect of multiple-failure events on accident management strategy for CANDU-6 reactors
Nuclear Engineering and Technology, 2021 Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failures should be considered more seriously rather than single failure in the licensing bases and safety cases because attempts to take accident management ...
Seon Oh YU, Manwoong KIM
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Frontiers in Energy Research, 2021 Under loss-of-coolant conditions, the temperature on fuel cladding will increase rapidly (up to 1000–1500 K), which will not only cause a dramatic oxidation reaction of Zircaloy-4 and an increase in hydrogen concentration but also cause an allotropic ...
Wenjun Lu +3 more
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Loss of coolant accident analysis under restriction of reverse flow
Nuclear Engineering and Technology, 2019 This paper analyzes a new method for reducing boiling water reactor fuel temperature during a Loss of Coolant Accident (LOCA). The method uses a device called Reverse Flow Restriction Device (RFRD) at the inlet of fuel bundles in the core to prevent ...
Majdi I. Radaideh +2 more
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Nonlinear dynamic analysis of nuclear fuels considering thermo–elastic–plastic–creep phenomena
Advances in Mechanical Engineering, 2016 Recently, research on the behavior of nuclear fuel rods in accident situations was performed. The research conducted was very sophisticated and involved complex tasks related to thermal, elastic, plastic, and creep phenomena.
Young-Doo Kwon +2 more
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Lead Halide Perovskite Photoelectrocatalysis
Advanced Materials, EarlyView.Lead halide perovskite semiconductors have emerged as highly promising materials for solar fuel and chemical synthesis. This perspective discusses advances made in the rational photoelectrode design to improve solar‐to‐chemical conversion, product scope, and scalability.
Virgil Andrei
wiley +1 more source
Simulation of loss-of-coolant accident with thin-walled cladding tubes
Nuclear Materials and EnergyA loss-of-coolant accident in a nuclear power plant was simulated in the CODEX-SLIM experiment. The electrically heated fuel rod bundle contained cladding material used at a VVER-440 power plant.
Róbert Farkas +8 more
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