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Nuclear Engineering and Technology  

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1 Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model
Korbu, Tamara;Kuzmin, Andrei;Rudak, Eduard;Kravchenko, Maksim; / Korean Nuclear Society , v.53, no.6, pp.1731-1735,
2 Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux
Bedenko, Sergey V.;Arzhannikov, Andrey V.;Lutsik, Igor O.;Prikhodko, Vadim V.;Shmakov, Vladimir M.;Modestov, Dmitry G.;Karengin, Alexander G.;Shamanin, Igor V.; / Korean Nuclear Society , v.53, no.6, pp.1736-1746,
3 FAST (floating absorber for safety at transient) for the improved safety of sodium-cooled burner fast reactors
Kim, Chihyung;Jang, Seongdong;Kim, Yonghee; / Korean Nuclear Society , v.53, no.6, pp.1747-1755,
4 Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle
Choi, Yu Jung;Kam, Dong Hoon;Papadopoulos, Petros;Lind, Terttaliisa;Jeong, Yong Hoon; / Korean Nuclear Society , v.53, no.6, pp.1756-1768,
5 Hot and average fuel sub-channel thermal hydraulic study in a generation III+ IPWR based on neutronic simulation
Gholamalishahi, Ramin;Vanaie, Hamidreza;Heidari, Ebrahim;Gheisari, Rouhollah; / Korean Nuclear Society , v.53, no.6, pp.1769-1785,
6 The optimization for the straight-channel PCHE size for supercritical CO2 Brayton cycle
Xu, Hong;Duan, Chengjie;Ding, Hao;Li, Wenhuai;Zhang, Yaoli;Hong, Gang;Gong, Houjun; / Korean Nuclear Society , v.53, no.6, pp.1786-1795,
7 Prediction of critical heat flux for narrow rectangular channels in a steady state condition using machine learning
Kim, Huiyung;Moon, Jeongmin;Hong, Dongjin;Cha, Euiyoung;Yun, Byongjo; / Korean Nuclear Society , v.53, no.6, pp.1796-1809,
8 Investigation of single bubble behavior under rolling motions using multiphase MPS method on GPU
Basit, Muhammad Abdul;Tian, Wenxi;Chen, Ronghua;Basit, Romana;Qiu, Suizheng;Su, Guanghui; / Korean Nuclear Society , v.53, no.6, pp.1810-1820,
9 Experimental study on air-water countercurrent flow limitation in a vertical tube based on measurement of film thickness behavior
Wan, Jie;Sun, Wan;Deng, Jian;Pan, Liang-ming;Ding, Shu-hua; / Korean Nuclear Society , v.53, no.6, pp.1821-1833,
10 Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead-bismuth
He, Shaopeng;Wang, Mingjun;Zhang, Jing;Tian, Wenxi;Qiu, Suizheng;Su, G.H.; / Korean Nuclear Society , v.53, no.6, pp.1834-1845,
11 Computational mechanics and optimization-based prediction of grain orientation in anisotropic media using ultrasonic response
Kim, Munsung;Moon, Seongin;Kang, To;Kim, Kyongmo;Song, Sung-Jin;Suh, Myungwon;Suhr, Jonghwan; / Korean Nuclear Society , v.53, no.6, pp.1846-1857,
12 Impact test of a centrifugal pump used in nuclear power plant under aircraft crash scenario
Huang, Tao;Chen, Mengmeng;Li, Zhongcheng;Dong, Zhanfa;Zhang, Tiejian;Zhou, Zhiguang; / Korean Nuclear Society , v.53, no.6, pp.1858-1868,
13 Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel
Narkunas, Ernestas;Smaizys, Arturas;Poskas, Povilas;Naumov, Valerij;Ekaterinichev, Dmitrij; / Korean Nuclear Society , v.53, no.6, pp.1869-1877,
14 Numerical estimation of errors in drop angle during drop tests of IP-Type metallic transport containers for radioactive materials
Lim, Jongmin;Yang, Yun Young;Lee, Ju-chan; / Korean Nuclear Society , v.53, no.6, pp.1878-1886,
15 Effect of gadolinium and boron addition on the texture development and magnetic properties of 23Cr-10NiCu duplex stainless steels
Baik, Youl;Kang, Bo Kyeong;Choi, Yong;Woo, Wan Chuck; / Korean Nuclear Society , v.53, no.6, pp.1887-1892,
16 A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors
Cechet, A.;Altieri, S.;Barani, T.;Cognini, L.;Lorenzi, S.;Magni, A.;Pizzocri, D.;Luzzi, L.; / Korean Nuclear Society , v.53, no.6, pp.1893-1908,
17 Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects
Park, Jae Phil;Yoo, Seung Chang;Kim, Ji Hyun;Bahn, Chi Bum; / Korean Nuclear Society , v.53, no.6, pp.1909-1923,
18 Fracture properties and crack tip constraint quantification of 321/690 dissimilar metal girth welded joints by using miniature SENB specimens
Bao, Chen;Sun, Yongduo;Wu, Yuanjun;Wang, Kaiqing;Wang, Li;He, Guangwei; / Korean Nuclear Society , v.53, no.6, pp.1924-1930,
19 Effect of oxygen containing compounds in uranium tetrafluoride on its non-adiabatic calciothermic reduction characteristics
Gupta, Sonal;Kumar, Raj;Satpati, Santosh K.;Sahu, Manharan L.; / Korean Nuclear Society , v.53, no.6, pp.1931-1938,
20 Study on sputtering yield of tungsten with different particle sizes: Surface roughness dependence
Kwon, Tae Hyun;Park, Sangjune;Ha, Jeong Min;Youn, Young-Sang; / Korean Nuclear Society , v.53, no.6, pp.1939-1941,
21 Study on the neutron imaging detector with high spatial resolution at China spallation neutron source
Jiang, Xingfen;Xiu, Qinglei;Zhou, Jianrong;Yang, Jianqing;Tan, Jinhao;Yang, Wenqin;Zhang, Lianjun;Xia, Yuanguang;Zhou, Xiaojuan;Zhou, Jianjin;Zhu, Lin;Teng, Haiyun;Yang, Gui-an;Song, Yushou;Sun, Zhijia;Chen, Yuanbo; / Korean Nuclear Society , v.53, no.6, pp.1942-1946,
22 Similarity analysis of pixelated CdTe semiconductor gamma camera image using a quadrant bar phantom for nuclear medicine: Monte Carlo simulation study
Park, Chan Rok;Kang, Seong-Hyeon;Lee, Youngjin; / Korean Nuclear Society , v.53, no.6, pp.1947-1954,
23 Investigation of a novel on-site U concentration analysis method for UO2 pellets using gamma spectroscopy
Lee, Haneol;Park, Chan Jong; / Korean Nuclear Society , v.53, no.6, pp.1955-1963,
24 Measurement of TOF of fast neutrons with 238U target
Li, Meng;Guan, Yuanfan;Lu, Chengui;Zhang, Junwei;Yuan, Xiaohua;Duan, Limin;Yang, Herun;Hu, Rongjiang;He, Zhiyong;Wei, Xianglun;Ma, Peng;Gan, Zaiguo;Yang, Chunli;Zhang, Hongbin;Chen, Liang;Qiu, Tianli;Hou, Yikai; / Korean Nuclear Society , v.53, no.6, pp.1964-1969,
25 Optimization of target, moderator, and collimator in the accelerator-based boron neutron capture therapy system: A Monte Carlo study
Cheon, Bo-Wi;Yoo, Dohyeon;Park, Hyojun;Lee, Hyun Cheol;Shin, Wook-Geun;Choi, Hyun Joon;Hong, Bong Hwan;Chung, Heejun;Min, Chul Hee; / Korean Nuclear Society , v.53, no.6, pp.1970-1978,
26 Cohort-based evacuation time estimation using TSIS-CORSIM
Park, Sunghyun;Sohn, Seokwoo;Jae, Moosung; / Korean Nuclear Society , v.53, no.6, pp.1979-1990,
27 Indirect assessment of internal irradiation from tritium decay on Lemna Minor duckweed
Ifayefunmi, O.S.;Mirseabasov, O.A.;Synzynys, B.I.; / Korean Nuclear Society , v.53, no.6, pp.1991-1999,
28 The influence of MgO on the radiation protection and mechanical properties of tellurite glasses
Hanfi, M.Y.;Sayyed, M.I.;Lacomme, E.;Akkurt, I.;Mahmoud, K.A.; / Korean Nuclear Society , v.53, no.6, pp.2000-2010,
29 Development of advanced rigorous two-step code system for evaluation of radioactive waste with high-resolution activation calculation
Kim, Do Hyun;Kim, Jiseok;Lee, Han Rim;Sun, Gwang Min;Shin, Chang Ho;Kim, Jong Kyung; / Korean Nuclear Society , v.53, no.6, pp.2011-2018,
30 Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling process
Lee, ChoongWie;Kim, Hee Reyoung;Lee, Seung Jun; / Korean Nuclear Society , v.53, no.6, pp.2019-2024,
31 An investigation of the nuclear shielding effectiveness of some transparent glasses manufactured from natural quartz doped lead cations
Kassem, Said M.;Ahmed, G.S.M.;Rashad, A.M.;Salem, S.M.;Ebraheem, S.;Mostafa, A.G.; / Korean Nuclear Society , v.53, no.6, pp.2025-2037,
32 Development of the structural health record of containment building in nuclear power plant
Chu, Shih-Yu;Kang, Chan-Jung; / Korean Nuclear Society , v.53, no.6, pp.2038-2045,
33 Identification of public concerns about radiation through a big data analysis of questions posted on a portal site in Korea
Jeong, So Yun;Kim, Jae Wook;Joo, Han Young;Kim, Young Seo;Moon, Joo Hyun; / Korean Nuclear Society , v.53, no.6, pp.2046-2055,
34 An empirical investigation of nuclear energy consumption and carbon dioxide (CO2) emission in India: Bridging IPAT and EKC hypotheses
Danish, Danish;Ozcan, Burcu;Ulucak, Recep; / Korean Nuclear Society , v.53, no.6, pp.2056-2065,
35 Energy optimization of a Sulfur-Iodine thermochemical nuclear hydrogen production cycle
Juarez-Martinez, L.C.;Espinosa-Paredes, G.;Vazquez-Rodriguez, A.;Romero-Paredes, H.; / Korean Nuclear Society , v.53, no.6, pp.2066-2073,