Results 21 to 30 of about 46,370 (246)

Applicability research of round tube CHF mechanistic model in rod bundle channel

open access: yesNuclear Engineering and Technology, 2021
In view of the complex geometric structure of the rod bundle channel and the limitation of the current CHF visualization experiment technology, it is very difficult to obtain the rod bundle CHF mechanism directly through the phenomenon of the rod bundle ...
Wei Liu   +6 more
doaj   +1 more source

Optimal design of a nuclear power plant condenser control system based on multi-objective optimization algorithm [PDF]

open access: yesNuclear Technology and Radiation Protection, 2020
A condenser control system of a nuclear power plant consists of a pressure control system, a condensate water sub-cooling degree control system and a water level control system.
Zhi Chen, Li Yiliang, Ke Huang, Kai Xiao
doaj   +1 more source

A method of X-ray source spectrum estimation from transmission measurements based on compressed sensing

open access: yesNuclear Engineering and Technology, 2020
A new method of X-ray source spectrum estimation based on compressed sensing is proposed in this paper. The algorithm K-SVD is applied for sparse representation.
Bin Liu   +6 more
doaj   +1 more source

Research on economic dispatch of integrated energy system based on improved krill swarm algorithm

open access: yesEnergy Reports, 2022
This paper constructs an economic dispatch model of an integrated energy system including grid, wind power, photovoltaic and energy storage devices based on combined cooling, heating and power system, and optimizes the dispatch model based on improved ...
Zhi-guang Deng   +5 more
doaj   +1 more source

Experimental study on aerosol behavior in water pool scrubbing under severe accident conditions

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2020
In severe accident of nuclear power plant, large quantities of steam and radioactive aerosol may release to the containment. Meanwhile, hydrogen may be generated by zirconium-steam reaction and released to the containment and mixed with steam and air to ...
Youyou Xu   +4 more
doaj   +1 more source

Optimization of preventive maintenance of nuclear safety-class DCS based on reliability modeling

open access: yesNuclear Engineering and Technology, 2022
Nuclear safety-class DCS is used for nuclear reactor protection function, which is one of the key facilities to ensure nuclear power plant safety, the maintenance for DCS to keep system in a high reliability is significant.
Hao Peng   +4 more
doaj   +1 more source

A Modified Multiobjective Self-Adaptive Differential Evolution Algorithm and Its Application on Optimization Design of the Nuclear Power System

open access: yesScience and Technology of Nuclear Installations, 2019
A modified multiobjective self-adaptive differential evolution algorithm (MMOSADE) is presented in this paper to improve the accuracy of multiobjective optimization design in the nuclear power system.
Yunjia Yang   +6 more
doaj   +1 more source

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

open access: yesScience and Technology of Nuclear Installations, 2021
In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based
Feng Li   +4 more
doaj   +1 more source

KRUSTY Reactor Design [PDF]

open access: yesNuclear Technology, 2020
The Kilowatt Reactor Using Stirling TechnologY (KRUSTY) was a reactor design, development, and test program to demonstrate the nuclear operation of a Kilopower reactor.
David I. Poston   +3 more
openaire   +1 more source

Analysis of Kobayashi benchmark with indigenous Monte Carlo neutron transport code PATMOC

open access: yesPhysics Open, 2023
The solution of the neutron transport equation is the basic input for the reactor physics design of a nuclear reactor system. Because of the complexities of geometry and cross-section data, the neutron transport equation is generally solved using ...
Amod Kishore Mallick, Umasankari Kannan
doaj   +1 more source

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