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Nuclear Engineering and Technology  

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1 Overview of CSNS tantalum cladded tungsten solid Target-1 and Target-2
Wei, Shaohong;Zhang, Ruiqiang;Ji, Quan;Li, Changfeng;Zhou, Bin;Lu, Youlian;Xu, Jun;Zhou, Ke;Zhao, Chongguang;He, Ning;Yin, Wen;Liang, Tianjiao; / Korean Nuclear Society , v.54, no.5, pp.1535-1540,
2 Effective thermal conductivity model of porous polycrystalline UO2: A computational approach
Yoon, Bohyun;Chang, Kunok; / Korean Nuclear Society , v.54, no.5, pp.1541-1548,
3 Study of the mechanical properties and effects of particles for oxide dispersion strengthened Zircaloy-4 via a 3D representative volume element model
Kim, Dong-Hyun;Hong, Jong-Dae;Kim, Hyochan;Kim, Jaeyong;Kim, Hak-Sung; / Korean Nuclear Society , v.54, no.5, pp.1549-1559,
4 Effect of process parameters on the recovery of thorium tetrafluoride prepared by hydrofluorination of thorium oxide, and their optimization
Kumar, Raj;Gupta, Sonal;Wajhal, Sourabh;Satpati, S.K.;Sahu, M.L.; / Korean Nuclear Society , v.54, no.5, pp.1560-1569,
5 Creep strain modeling for alloy 690 SG tube material based on modified theta projection method
Moon, Seongin;Kim, Jong-Min;Kwon, Joon-Yeop;Lee, Bong-Sang;Choi, Kwon-Jae;Kim, Min-Chul; / Korean Nuclear Society , v.54, no.5, pp.1570-1578,
6 Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations
Bang, Shinhyo;Kim, Ho-a;Noh, Jae-soo;Kim, Donguk;Keum, Kyunghwan;Lee, Youho; / Korean Nuclear Society , v.54, no.5, pp.1579-1587,
7 Prediction of fatigue crack initiation life in SA312 Type 304LN austenitic stainless steel straight pipes with notch
Murthy, A. Ramachandra;Vishnuvardhan, S.;Anjusha, K.V.;Gandhi, P.;Singh, P.K.; / Korean Nuclear Society , v.54, no.5, pp.1588-1596,
8 Recovery of cesium ions from seawater using a porous silica-based ionic liquid impregnated adsorbent
Wu, Hao;Kudo, Tatsuya;Kim, Seong-Yun;Miwa, Misako;Matsuyama, Shigeo; / Korean Nuclear Society , v.54, no.5, pp.1597-1605,
9 Novel approach to predicting the release probability when applying the MARSSIM statistical test to a survey unit with a specific residual radioactivity distribution based on Monte Carlo simulation
Chun, Ga Hyun;Cheong, Jae Hak; / Korean Nuclear Society , v.54, no.5, pp.1606-1615,
10 Sorption of Se(-II) on illite, MX-80 bentonite, shale, and limestone in Na-Ca-Cl solutions
Walker, Andrew;Racette, Joshua;Saito, Takumi;Yang, Tammy (Tianxiao);Nagasaki, Shinya; / Korean Nuclear Society , v.54, no.5, pp.1616-1622,
11 Development of a gamma irradiation loop to evaluate the performance of a EURO-GANEX process
Sanchez-Garcia, I.;Galan, H.;Nunez, A.;Perlado, J.M.;Cobos, J.; / Korean Nuclear Society , v.54, no.5, pp.1623-1634,
12 A formal approach to support the identification of unsafe control actions of STPA for nuclear protection systems
Jung, Sejin;Heo, Yoona;Yoo, Junbeom; / Korean Nuclear Society , v.54, no.5, pp.1635-1643,
13 Adaptive second-order nonsingular terminal sliding mode power-level control for nuclear power plants
Hui, Jiuwu;Yuan, Jingqi; / Korean Nuclear Society , v.54, no.5, pp.1644-1651,
14 Experimental testing and evaluation of coating on cables in container fire test facility
Aurtherson, P. Babu;Hemanandh, J.;Devarajan, Yuvarajan;Mishra, Ruby;Abraham, Biju Cherian; / Korean Nuclear Society , v.54, no.5, pp.1652-1656,
15 Nuclear energy consumption and CO2 emissions in India: Evidence from Fourier ARDL bounds test approach
Ozgur, Onder;Yilanci, Veli;Kongkuah, Maxwell; / Korean Nuclear Society , v.54, no.5, pp.1657-1663,
16 Evaluating the asymmetric effects of nuclear energy on carbon emissions in Pakistan
Majeed, Muhammad Tariq;Ozturk, Ilhan;Samreen, Isma;Luni, Tania; / Korean Nuclear Society , v.54, no.5, pp.1664-1673,
17 Transient simulation and experiment validation on the opening and closing process of a ball valve
Han, Yong;Zhou, Ling;Bai, Ling;Xue, Peng;Lv, Wanning;Shi, Weidong;Huang, Gaoyang; / Korean Nuclear Society , v.54, no.5, pp.1674-1685,
18 SACADA and HuREX: Part 1. the use of SACADA and HuREX systems to collect human reliability data
Chang, Yung Hsien James;Kim, Yochan;Park, Jinkyun;Criscione, Lawrence; / Korean Nuclear Society , v.54, no.5, pp.1686-1697,
19 Application of a combined safety approach for the evaluation of safety margin during a Loss of Condenser Vacuum event
Shin, Dong-Hun;Jeong, Hae-Yong;Park, Moon-Ghu;Sohn, Jung-Uk; / Korean Nuclear Society , v.54, no.5, pp.1698-1711,
20 Improvement on optimal design of dynamic absorber for enhancing seismic performance of nuclear piping using adaptive Kriging method
Kwag, Shinyoung;Eem, Seunghyun;Kwak, Jinsung;Lee, Hwanho;Oh, Jinho;Koo, Gyeong-Hoi; / Korean Nuclear Society , v.54, no.5, pp.1712-1725,
21 Constraint-corrected fracture mechanics analysis of nozzle crotch corners in pressurized water reactors
Kim, Jong-Sung;Seo, Jun-Min;Kang, Ju-Yeon;Jang, Youn-Young;Lee, Yun-Joo;Kim, Kyu-Wan; / Korean Nuclear Society , v.54, no.5, pp.1726-1746,
22 Application of a deep learning algorithm to Compton imaging of radioactive point sources with a single planar CdTe pixelated detector
Daniel, G.;Gutierrez, Y.;Limousin, O.; / Korean Nuclear Society , v.54, no.5, pp.1747-1753,
23 Source and LVis based coincidence summing correction in HPGe gamma-ray spectrometry
Lee, Jieun;Kim, HyoJin;Kye, Yong Uk;Lee, Dong Yeon;Kim, Jeung Kee;Jo, Wol Soon;Kang, Yeong-Rok; / Korean Nuclear Society , v.54, no.5, pp.1754-1759,
24 Improving light collection efficiency using partitioned light guide on pixelated scintillator-based γ-ray imager
Hyeon, Suyeon;Hammig, Mark;Jeong, Manhee; / Korean Nuclear Society , v.54, no.5, pp.1760-1768,
25 Development of a dose estimation code for BNCT with GPU accelerated Monte Carlo and collapsed cone Convolution method
Lee, Chang-Min;Lee Hee-Seock; / Korean Nuclear Society , v.54, no.5, pp.1769-1780,
26 External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 1
Byon, Jihyang;Park, Sangjune;Kim, Yangjin;Ahn, Seokyoung; / Korean Nuclear Society , v.54, no.5, pp.1781-1788,
27 Verification of a two-step code system MCS/RAST-F to fast reactor core analysis
Tran, Tuan Quoc;Cherezov, Alexey;Du, Xianan;Lee, Deokjung; / Korean Nuclear Society , v.54, no.5, pp.1789-1803,
28 A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
Dokhane, A.;Vasiliev, A.;Hursin, M.;Rochman, D.;Ferroukhi, H.; / Korean Nuclear Society , v.54, no.5, pp.1804-1812,
29 Verification of SARAX code system in the reactor core transient calculation based on the simplified EBR-II benchmark
Jia, Xiaoqian;Zheng, Youqi;Du, Xianna;Wang, Yongping;Chen, Jianda; / Korean Nuclear Society , v.54, no.5, pp.1813-1824,
30 Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles
Kang, Huilun;Tian, Zhaofei;Chen, Guangliang;Li, Lei;Chu, Tianhui; / Korean Nuclear Society , v.54, no.5, pp.1825-1834,
31 Cavitation optimization of single-orifice plate using CFD method and neighborhood cultivation genetic algorithm
Zhang, Yu;Lai, Jiang;He, Chao;Yang, Shihao; / Korean Nuclear Society , v.54, no.5, pp.1835-1844,
32 Can a nanofluid enhance the critical heat flux if the recirculating coolant contains debris?
Han, Jihoon;Nam, Giju;Kim, Hyungdae; / Korean Nuclear Society , v.54, no.5, pp.1845-1850,
33 Experiment investigation on flow characteristics of open natural circulation system
Qi, Xiangjie;Zhao, Zichen;Ai, Peng;Chen, Peng;Sun, Zhongning;Meng, Zhaoming; / Korean Nuclear Society , v.54, no.5, pp.1851-1859,
34 Comparative study of constitutive relations implemented in RELAP5 and TRACE - Part II: Wall boiling heat transfer
Shin, Sung Gil;Lee, Jeong Ik; / Korean Nuclear Society , v.54, no.5, pp.1860-1873,
35 Evaluation of thermal-hydraulic performance and economics of Printed Circuit Heat Exchanger (PCHE) for recuperators of Sodium-cooled Fast Reactors (SFRs) using CO2 and N2 as working fluids
Lee, Su Won;Shin, Seong Min;Chung, SungKun;Jo, HangJin; / Korean Nuclear Society , v.54, no.5, pp.1874-1889,
36 Development of a special thermal-hydraulic component model for the core makeup tank
Kim, Min Gi;Wisudhaputra, Adnan;Lee, Jong-Hyuk;Kim, Kyungdoo;Park, Hyun-Sik;Jeong, Jae Jun; / Korean Nuclear Society , v.54, no.5, pp.1890-1901,
37 Performing linear regression with responses calculated using Monte Carlo transport codes
Price, Dean;Kochunas, Brendan; / Korean Nuclear Society , v.54, no.5, pp.1902-1908,
38 Uranium tetrafluoride production at pilot scale using a mercury electrode cell
Dides, Munir;Hernandez, Jose;Olivares, Luis; / Korean Nuclear Society , v.54, no.5, pp.1909-1913,
39 Numerical investigation of the critical heat flux in a 5 × 5 rod bundle with multi-grid
Liu, Wei;Shang, Zemin;Yang, Shihao;Yang, Lixin;Tian, Zihao;Liu, Yu;Chen, Xi;Peng, Qian; / Korean Nuclear Society , v.54, no.5, pp.1914-1928,
40 On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation
Romano, M.;Pizzocri, D.;Luzzi, L.; / Korean Nuclear Society , v.54, no.5, pp.1929-1934,