ScholarWorks@Korea University

Nuclear Engineering and Technology open-access icon

Journal Title

  • Nuclear Engineering and Technology

ISSN

  • P 1738-5733 | 1738-5733

Publisher

  • 한국원자력학회
  • Korean Nuclear Society

Listed on(Coverage)

JCR2009-2019
SJR2009-2019
CiteScore2011-2019
SCIE2010-2021
SCOPUS2017-2020
DOAJ2017-2021
KCI(Ranking)2009-2019
KCI2004-2021
KCI(Candidate)1999-2003

OA Info.

OAopen-access icon

based on the information

  • 2017;2018;2019;2020;2021;
Keywordsreactor physics, nuclear safety, nuclear fuel cycle, nuclear fuel and reactor materials, radiation applications, nuclear i&c
Review ProcessBlind peer review
Journal info. pages
LicencesCC BY, CC BY-NC-ND
CopyrightsNo
DOAJ Coverage
  • Added on Date : 2016-11-11T13:27:33Z
Subject(s)Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power

Active

  • Active

    based on the information

    • SCOPUS:2020-10

Country

  • SOUTH KOREA

Article List

1 - 20 out of 24 results.

SCIESCOPUS
Effect of strain rate and stress triaxiality on fracture strain of 304 stainless steels for canister impact simulationopen access

Seo, Jun-Min; Kim, Hune-Tae; Kim, Yun-Jae; Yamada, Hiroyuki; Kumagai, Tomohisa; Tokunaga, Hayato; Miura, Naoki

ArticleIssue Date2022CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.7, pp.2386 - 2394PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Effect of material hardening model for canister on finite element cask drop simulation for strain-based acceptance evaluation

Kim, Hune-Tae; Seo, Jun-Min; Seo, Ki-Wan; Yoon, Seong-Ho; Kim, Yun-Jae; Oh, Chang-Young

ArticleIssue Date2022CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.3, pp.1098 - 1108PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Efficient elastic stress analysis method for piping system with wall-thinning and reinforcement

Kim, Ji-Su; Jang, Je-Hoon; Kim, Yun-Jae

ArticleIssue Date2022CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.2, pp.732 - 740PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
p Round robin analysis to investigate sensitivity of analysis results to finite element elastic-plastic analysis variables for nuclear safety class 1 components under severe seismic load

Kim, Jun-Young; Lee, Jong Min; Park, Jun Geun; Kim, Jong-Sung; Cho, Min Ki; Ahn, Sang Won; Koo, Gyeong-Hoi; Lee, Bong Hee; Huh, Nam-Su; Kim, Yun-Jae, et al.

ArticleIssue Date2022CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.1, pp.343 - 356PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Evaluation of sequence tracking methods for Compton cameras based on CdZnTe arrays

Lee, Jun; Kim, Younghak; Bolotnikov, Aleksey; Lee, Wonho

ArticleIssue Date2021CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.12, pp.4080 - 4092PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Fatigue life evaluation of socket welded pipe with incomplete penetration defect: I-test and FE analysis

Lee, Dong-Min; Kim, Seung-Jae; Lee, Hyun-Jae; Kim, Yun-Jae

ArticleIssue Date2021CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.11, pp.3852 - 3859PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
High performance gamma-ray imager using dual anti-mask method for the investigation of high-energy nuclear materials

Lee, Taewoong; Lee, Wonho

ArticleIssue Date2021CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.7, pp.2371 - 2376PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Thermal aging effect on fracture toughness of GTAW/SMAW of 316L stainless steel: experiments and applicability of existing CASS models

Youn, G.-G.; Kim, Y.-J.; Miura, Y.

ArticleIssue Date2021CitationNuclear Engineering and Technology, v.53, no.4, pp.1357 - 1368PublisherKorean Nuclear Society
SCIESCOPUSKCI
Fracture simulation of SFR metallic fuel pin using finite element damage analysis method

Jung, Hyun-Woo; Song, Hyun-Kyu; Kim, Yun-Jae; Jerng, Dong-Wook

ArticleIssue Date2021CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.3, pp.932 - 941PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Design of a scintillator-based prompt gamma camera for boron-neutron capture therapy: Comparison of SrI2 and GAGG using Monte-Carlo simulation

Kim, Minho; Hong, Bong Hwan; Cho, Ilsung; Park, Chawon; Min, Sun-Hong; Hwang, Won Taek; Lee, Wonho; Kim, Kyeong Min

ArticleIssue Date2021CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.2, pp.626 - 636PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Burst pressure estimation of Alloy 690 axial cracked steam generator U-bend tubes using finite element damage analysis

Kim, Ji-Seok; Kim, Yun-Jae; Lee, Myeong-Woo; Jeon, Jun-Young; Kim, Jong-Sung

ArticleIssue Date2021CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.2, pp.666 - 676PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Effect of critical flow model in MARS-KS code on uncertainty quantification of large break Loss of coolant accident (LBLOCA)

Lee, Ilsuk; Oh, Deogyeon; Bang, Youngseog; Kim, Yongchan

ArticleIssue Date2020CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.4, pp.755 - 763PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Radiation measurement and imaging using 3D position sensitive pixelated CZT detector

Kim, Younghak; Lee, Taewoong; Lee, Wonho

ArticleIssue Date2019CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.5, pp.1417 - 1427PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks

Kim, Ji-Seok; Lee, Myeong-Woo; Kim, Yun-Jae; Kim, Jin-Weon

ArticleIssue Date2019CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.2, pp.579 - 587PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Effects of collimator on imaging performance of Yttrium-90 Bremsstrahlung photons: Monte Carlo simulation

Kim, Minho; Bae, Jae Keon; Hong, Bong Hwan; Kim, Kyeong Min; Lee, Wonho

ArticleIssue Date2019CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.2, pp.539 - 545PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Investigation of nuclear material using a compact modified uniformly redundant array gamma camera

Lee, Taewoong; Kwak, Sung-Woo; Lee, Wonho

ArticleIssue Date2018CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.50, no.6, pp.923 - 928PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Experimental Study on the Shrinkage Properties and Cracking Potential of High Strength Concrete Containing Industrial By-Products for Nuclear Power Plant Concrete

Kim, Baek-Joong; Yi, Chongku

ArticleIssue Date2017CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.49, no.1, pp.224 - 233PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Effect of Loading Rate on the Fracture Behavior of Nuclear Piping Materials Under Cyclic Loading Conditions

Kim, Jin Weon; Choi, Myung Rak; Kim, Yun Jae

ArticleIssue Date2016CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.6, pp.1376 - 1386PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
Numerical Ductile Tearing Simulation of Circumferential Cracked Pipe Tests under Dynamic Loading Conditions

Nam, Hyun-Suk; Kim, Ji-Soo; Ryu, Ho-Wan; Kim, Yun-Jae; Kim, Jin-Weon

ArticleIssue Date2016CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.5, pp.1252 - 1263PublisherKOREAN NUCLEAR SOC
SCIESCOPUSKCI
PWSCC Growth Assessment Model Considering Stress Triaxiality Factor for Primary Alloy 600 Components

Kim, Jong-Sung; Kim, Ji-Soo; Jeon, Jun-Young; Kim, Yun-Jae

ArticleIssue Date2016CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.4, pp.1036 - 1046PublisherKOREAN NUCLEAR SOC
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