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전체 가 나 다 라 마 바 사 아 자 차 카 타 파 하

Showing results 1 to 20 of 95

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3.5 MeV 양성자 조사에 의한 철(Fe)의 조사손상 영향 연구Go to Link

Chae, San; Rafique, Mohsin; Kim, Yong-soo

ArticleIssue Date2016Citation대한금속·재료학회지, v.54, no.1, pp 63 - 67Publisher대한금속·재료학회
SCIESCOPUSKCI
A Review of Factors Influencing the Hydride Reorientation Phenomena in Zirconium Alloy Cladding During Long-Term Dry StorageGo to Link

Lee, Ji Min; Kim, Ho A; Kook, Dong Hak; Kim, Yong Soo

ArticleIssue Date2018Citation대한금속·재료학회지, v.56, no.2, pp 79 - 92Publisher대한금속·재료학회
A Review on Stress Corrosion Cracking of Stainless Steel 316L in Oxygenated and Chlorinated Primary Water Chemistry

김용수

ConferenceIssue Date2020Citation2020 춘계 원자력학회Publisher한국원자력학회Place온라인
A Study of the Nuclear Inventory Evaluation for Decommissioning Radioactive Waste Scaling Factor Analysis

김용수

ConferenceIssue Date2020Citation2020 추계 한국방사성폐기물학회Publisher한국방사성폐기물학회Place온라인
SCIESCOPUSKCI
A study on DCGL determination and the classification of contaminated areas for preliminary decommission planning of KEPCO-NF nuclear fuel fabrication facilityGo to Linkopen access

Cho, Seo-Yeon; Kim, Yong-Soo; Park, Da-Won; Park, Chan-Jun

ArticleIssue Date2019CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.8, pp.1951 - 1956PublisherKOREAN NUCLEAR SOC
A study on effects of hydrogen content and peak temperature on threshold stress for hydride reorientation

김용수

ConferenceIssue Date2017Citation4th Asian Zirconium WorkshopPublisherAsian Zirconium Workshop
SCISCIESCOPUS
A study on hydride reorientation of Zircaloy-4 cladding tube under stressGo to Link

Kim, Ju-Seong; Kim, Young-Jun; Kook, Dong-Hak; Kim, Yong-Soo

ArticleIssue Date2015CitationJournal of Nuclear Materials, v.456, pp 246 - 252PublisherElsevier BV
SCIESCOPUS
A study on in-situ characterization technology development for clearance verification of radioactive waste from nuclear decommissioningGo to Link

Kim, Kyungmin; Ko, Minseung; Kim, Sangtae; Kim, Yongsoo

ArticleIssue Date2025CitationAnnals of Nuclear Energy, v.211, pp 1 - 12PublisherElsevier Ltd.
SCIESCOPUSKCI
A STUDY ON THE AGING DEGRADATION OF ETHYLENE-PROPYLENE-DIENE MONOMER (EPDM) UNDER LOCA CONDITIONGo to Link

Seo, Yong-Dae; Lee, Hyun-Seon; Kim, Yong-Soo; Song, Chisung

ArticleIssue Date2011CitationNuclear Engineering and Technology, v.43, no.3, pp 279 - 286Publisher한국원자력학회
SCISCIESCOPUS
A study on the effects of dissolved hydrogen on zirconium alloys corrosionGo to Link

Kim, Yong-soo; Jeong, Yong-hwan; Son, Seung-beom

ArticleIssue Date2014CitationJournal of Nuclear Materials, v.444, no.1-3, pp 349 - 355PublisherElsevier BV
SCIESCOPUSKCI
A STUDY ON THE INITIAL CHARACTERISTICS OF DOMESTIC SPENT NUCLEAR FUELS FOR LONG TERM DRY STORAGEGo to Link

Kim, Juseong; Yoon, Hakkyu; Kook, Donghak; Kim, Yongsoo

ArticleIssue Date2013CitationNuclear Engineering and Technology, v.45, no.3, pp 377 - 384Publisher한국원자력학회
SCIESCOPUS
A Study on the NF3 Plasma Etching Reaction with Cobalt Oxide Grown on Inconel Base Metal SurfaceGo to Link

Lee, Jaeyong; Kim, Kyungmin; Kim, Yong-Soo

ArticleIssue Date2019CitationPLASMA CHEMISTRY AND PLASMA PROCESSING, v.39, no.4, pp.1145 - 1159PublisherSPRINGER
A Study on the Optimized Segmentation of 560 MWe Westinghouse Pressurized Water Reactor Vessel Internals

김용수

ConferenceIssue Date2020Citation2020 추계 한국방사성폐기물학회Publisher한국방사성폐기물학회Place온라인
A Study on the Peening Effects of 316LN Stainless Steel Using the Contour Method to Enhance the SCC (Stress Corrosion Cracking) Resistance for SNF Dry Storage Canisters

김용수

ConferenceIssue Date2020Citation2020 추계 한국방사성폐기물학회Publisher한국방사성폐기물학회Place온라인
A Study on the Radial Hydride Assisted Delayed Hydride Cracking of ZircaloyGo to Link

Jeong, Jin-Ho; Lee, Ji-Min; Kim, Yong-Soo

ConferenceIssue Date2015CitationThe KNS 2015 spring meeting, pp.1 - 2PublisherKorean Nuclear SocietyPlaceKO; Jeju
SCISCIESCOPUS
A study on the reaction of Zircaloy-4 tube with hydrogen/steam mixtureGo to Link

Lee, Ji Min; Kook, Dong Hak; Cho, Il Je; Kim, Yong Soo

ArticleIssue Date2017CitationJournal of Nuclear Materials, v.491, pp 105 - 114PublisherElsevier BV
A Study on the Review of Concrete Waste Generated by Decommissioning of Nuclear Power Plant

김용수

ConferenceIssue Date2020Citation2020 춘계 원자력학회Publisher한국원자력학회Place온라인
A Study on the Secondary Hydriding Mechanism of Zirconium Alloy Cladding

김용수

ConferenceIssue Date2017CitationWater Reactor Fuel Performance MeetingPublisherWater Reactor Fuel Performance Meeting
Accident Case Analysis for Safety Assessment of Decommissioning

김용수

ConferenceIssue Date2017Citation한국방사성폐기물학회Publisher한국방사성폐기물학회
Analysis of Radiation Damage on Fe-Cr alloy using Monte Carlo Method

김용수

ConferenceIssue Date2014CitationIYNC2014, pp.1 - 2PublisherInternational Youth Nuclear CongressPlaceSP; Burgos
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