Results 61 to 70 of about 6,875,634 (190)
Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors
A neutronics/thermal‐hydraulics (TH) coupled spatial dynamics code, reactor system transient analysis‐three dimensional (RESTA‐3D), has been developed for both static and transient analysis of large advanced light water reactors (LWRs), with a focus on control rod (CR) ejection accidents.
Yong Cui +4 more
wiley +1 more source
The load control of a nuclear reactor is important due to the nonlinear nature of its dynamics and the dependence of some parameters on the output power. the Proportional-Integral-Derivative controller (PID) is commonly regarded as an easy choice for reliable control.
openaire +1 more source
Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases [PDF]
The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications.
Avramova, Maria, Cuervo Gómez, Diana
core
Fluidized bed membrane reactors
Fluidized bed membrane reactors are an extension or an improvement of a packed bed membrane reactor. The fluidized bed configuration allows a more uniform temperature due to the movement of particles even for very exothermic reactions and decreased ...
Gallucci, Fausto +1 more
core +1 more source
Background. The commissioning of new nuclear power plants with WWER-1200 water-water energetic reactors, including the Akkuyu Nuclear Power Plant, requires a high level of operational safety and seismic resistance.
Konstantin N. Proskuryakov +2 more
doaj +1 more source
In the context of severe nuclear accidents, the migration of corium into the reactor pressure vessel (RPV) poses significant hazards, prompting the proposal of the in‐vessel melt retention (IVR) strategy, particularly the external reactor vessel cooling (ERVC) approach.
Pengya Guo +6 more
wiley +1 more source
In molten salt reactors (MSRs), a small amount of inert gas could be entrained from the free liquid surface to the primary loop, which may have obvious impacts on the heat transfer performance of the heat exchanger, the reactivity of the core, and the migration of insoluble fission products.
Ziye Wang +6 more
wiley +1 more source
A Global Review of PWR Nuclear Power Plants [PDF]
[Abstract] Nuclear energy is presented as a real option in the face of the current problem of climate change and the need to reduce CO2 emissions. The nuclear reactor design with the greatest global impact throughout history and which has the most ...
José A. Orosa +5 more
core +1 more source
Regression analysis of nuclear plant capacity factors
Operating data on all commercial nuclear power plants of the PWR, HWR, BWR, and GCR types in the Western World are analysed statistically to determine whether the explanatory variables size year of operation vintage and reactor supplier are significant ...
Stocks, KJ, Faulkner, JI
core
Operating strategies for variable-flow sequencing batch reactors. [PDF]
Sequencing batch reactors (SBRs) are variable-volume, non-steady-state, suspended-growth biological wastewater treatment reactors. The treatment process is characterised by a repeated treatment cycle consisting of a series of sequential process phases ...
Stephenson, Tom +5 more
core +1 more source

