Results 61 to 70 of about 176 (127)

Improved reactor regulating system logical architecture using genetic algorithm

open access: yesNuclear Engineering and Technology, 2017
An improved Reactor Regulating System (RRS) logic architecture, which is combined with genetic algorithm (GA), is implemented in this work. It is devised to provide an optimal solution to the current RRS.
Hyo-Sub Shim, Jae-Chun Jung
doaj   +1 more source

Analysis of the APR1400 Benchmark Using High-Fidelity Pin-Wise Core Calculation Codes

open access: yesEnergies
The KEPCO Nuclear Fuel Company (KNF) has undertaken considerable efforts to improve the KARMA/ASTRA nuclear design code system to meet the increasing demand for high-fidelity core analyses.
Hwanyeal Yu, Hyunsik Hong, Jooil Yoon
doaj   +1 more source

Research efforts for the resolution of hydrogen risk

open access: yesNuclear Engineering and Technology, 2015
During the past 10 years, the Korea Atomic Energy Research Institute (KAERI) has performed a study to control hydrogen gas in the containment of the nuclear power plants.
Seong-Wan Hong   +4 more
doaj   +1 more source

Extended Battery to Cope with ELAP for APR1400 [PDF]

open access: yesJournal of Energy and Power Engineering, 2017
null Hamdy Samier Hamdy Abdelbadea   +1 more
openaire   +1 more source

Monte Carlo Modeling of Isotopic Changes of Actinides in Nuclear Fuel of APR1400 Pressurized Water Reactor

open access: yesEnergies
The aim of this paper is to present the isotopic changes in nuclear fuel during the first reactor cycle of the Korean Advanced Power Reactor 1400 (APR1400).
Mikołaj Oettingen, Juyoul Kim
doaj   +1 more source

DEVELOPMENT OF AN IMPROVED INSTALLATION PROCEDURE AND SCHEDULE OF RVI MODULARIZATION FOR APR1400 [PDF]

open access: yesNuclear Engineering and Technology, 2011
The construction technology for reactor vessel internals (RVI) modularization is one of the most important factors to be considered in reducing the construction period of nuclear power plants. For RVI modularization, gaps between the reactor vessel (RV) core-stabilizing lug and the core support barrel (CSB) snubber lug must be measured using a remote ...
openaire   +1 more source

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