Results 21 to 30 of about 848 (238)
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
doaj +1 more source
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
doaj +1 more source
Hydraulic transients for loss of coolant accidents [PDF]
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
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
openaire +2 more sources
Effect of multiple-failure events on accident management strategy for CANDU-6 reactors
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
doaj +1 more source
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
doaj +1 more source
Loss of coolant accident analysis under restriction of reverse flow
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
doaj +1 more source
Nonlinear dynamic analysis of nuclear fuels considering thermo–elastic–plastic–creep phenomena
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
doaj +1 more source
Lead Halide Perovskite Photoelectrocatalysis
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
A 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
doaj +1 more source

