Feasibility of an integrated steam generator system in a sodium-cooled fast reactor subjected to elevated temperature services
Gyeong-Hoi Koo,Jae-Han Lee +1 more
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In this article, the concept of an integrated steam generator and pump system (ISGPS) is proposed from a structural point of view and the related intermediate heat transfer system (IHTS) piping layout compatible with the ISGPS is described in detail.About:
This article is published in Nuclear Engineering and Technology.The article was published on 2009-10-31 and is currently open access. It has received 5 citations till now. The article focuses on the topics: Sodium-cooled fast reactor & Boiler (power generation).read more
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An engineering scale study on radiation grafting of polymeric adsorbents for recovery of heavy metal ions from seawater
TL;DR: In this article, a scheme was designed and developed for investigation of the recovery of heavy metal ions such as uranium and vanadium from seawater, and the grafted polyacrylonitrile chains were chemically modified to convert acrylatitrile group into an amidoxime group, a chelating group responsible for heavy metal uptake from seawaters/brine.
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Deformation Characteristics and Sealing Performance of Metallic O-rings for a Reactor Pressure Vessel
TL;DR: In this article, a nonlinear elastic-plastic model of an O-ring was constructed by the finite element method to analyze its intrinsic properties and validated by experiments on scaled-samples.
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A stress analysis for a coated fuel particle of a htgr using a finite element method
Young-Min Kim,Moon Sung Cho +1 more
TL;DR: In this article, a finite element method utilizing the Galerkin form of the weighted residuals procedure was developed to estimate the mechanical behavior for a coated fuel particle (CFP) of a high temperature gas-cooled reactor (HTGR).
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Simulation of high burnup structure in uo₂ using potts model
TL;DR: In this article, the evolution of a high burnup structure (HBS) in a light water reactor (LWR) UO₂ fuel was simulated using the Potts model, where the stored energy was calculated from both the irradiation damage of the UO matrix and the formation of a grain boundary in the newly recrystallized small HBS grains.
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Evaluation of a penetration-reinforcing agent to prevent the aging of concrete
TL;DR: In this paper, a penetration-reinforcing agent has been proposed to increase the compressive strength by filling up the internal pores of concrete with physically and chemically stable compounds after penetrating the concrete.
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Westinghouse AP1000 advanced passive plant
TL;DR: The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the US deregulated electrical power industry in the near-term as discussed by the authors, and the AP1000 is a two-loop 1000 MWe pressurizer water reactor (PWR).
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A next generation sodium-cooled fast reactor concept and its r&d program
TL;DR: A promising design concept of sodium-cooled fast reactor JSFR is proposed aiming at fully satisfaction of the development targets for the next generation nuclear energy system in this article, where a roadmap toward JSFR commercialization is described, to be followed up in a new framework of the Fast reactor Cycle Technology development(FaCT) Project launched in 2006.
Journal Article
Elevated Temperature Design of KALIMER Reactor Internals Accounting for Creep and Stress-Rupture Effects
Gyeong-Hoi Koo,Bong Yoo +1 more
TL;DR: In this paper, an elevated temperature design of the conceptually designed baffle annulus regions of KALIMER (Korea Advanced Liquid MEtal Reactor) reactor internal strictures is carried out for normal operating conditions which have the operating temperature 53 and the total service lifetime of 30 years.
Journal Article
Evaluation of Creep-Fatigue Damage of KALIMER Reactor Internals Using the Elastic Analysis Method in RCC-MR
Gyeong-Hoi Koo,Bong Yoo +1 more
TL;DR: In this article, the effects of thermal induced membrane stress on the creep-fatigue damage are investigated with the risk of the elastic follow-up using the RCC-MR code for normal operating conditions including the thermal load, seismic load (OBE), and dead weight.