Browse > Article List
학술지 정보
Nuclear Engineering and Technology  

논문
1 Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS code
Dos, Vutheam;Lee, Hyunsuk;Jo, Yunki;Lemaire, Matthieu;Kim, Wonkyeong;Choi, Sooyoung;Zhang, Peng;Lee, Deokjung; / Korean Nuclear Society , v.52, no.9, pp.1881-1895,
2 BEAVRS benchmark analyses by DeCART stand-alone calculations and comparison with DeCART/MATRA multi-physics coupling calculations
Park, Ho Jin;Kim, Seong Jin;Kwon, Hyuk;Cho, Jin Young; / Korean Nuclear Society , v.52, no.9, pp.1896-1906,
3 Validation of nuclide depletion capabilities in Monte Carlo code MCS
Ebiwonjumi, Bamidele;Lee, Hyunsuk;Kim, Wonkyeong;Lee, Deokjung; / Korean Nuclear Society , v.52, no.9, pp.1907-1916,
4 Criticality benchmarking of ENDF/B-VIII.0 and JEFF-3.3 neutron data libraries with RMC code
Zheng, Lei;Huang, Shanfang;Wang, Kan; / Korean Nuclear Society , v.52, no.9, pp.1917-1925,
5 Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data
Yoon, Ho Joon;Al Naqbi, Waleed;Al-Yahia, Omar S.;Jo, Daeseong; / Korean Nuclear Society , v.52, no.9, pp.1926-1938,
6 Pool boiling heat transfer of a copper microporous coating in borated water
Jun, Seongchul;Godinez, Juan C.;You, Seung M.;Kim, Hwan Yeol; / Korean Nuclear Society , v.52, no.9, pp.1939-1944,
7 Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method
Ju, Haoran;Wang, Mingjun;Wang, Yingjie;Zhao, Minfu;Tian, Wenxi;Liu, Tiancai;Su, G.H.;Qiu, Suizheng; / Korean Nuclear Society , v.52, no.9, pp.1945-1954,
8 Experimental and numerical investigations on effect of reverse flow on transient from forced circulation to natural circulation
Li, Mingrui;Chen, Wenzhen;Hao, Jianli;Li, Weitong; / Korean Nuclear Society , v.52, no.9, pp.1955-1962,
9 Experimental validation of simulating natural circulation of liquid metal using water
Lee, Min Ho;Jerng, Dong Wook;Bang, In Cheol; / Korean Nuclear Society , v.52, no.9, pp.1963-1973,
10 POSCA: A computer code for fission product plateout and circulating coolant activities within the primary circuit of a high temperature gas-cooled reactor
Tak, Nam-il;Lee, Jeong-Hun;Lee, Sung Nam;Jo, Chang Keun; / Korean Nuclear Society , v.52, no.9, pp.1974-1982,
11 A plant-specific HRA sensitivity analysis considering dynamic operator actions and accident management actions
Kancev, Dusko; / Korean Nuclear Society , v.52, no.9, pp.1983-1989,
12 MNSR transient analysis using the RELAP5/Mod3.2 code
Dawahra, S.;Khattab, K.;Alhabit, F.; / Korean Nuclear Society , v.52, no.9, pp.1990-1997,
13 Fault state detection and remaining useful life prediction in AC powered solenoid operated valves based on traditional machine learning and deep neural networks
Utah, M.N.;Jung, J.C.; / Korean Nuclear Society , v.52, no.9, pp.1998-2008,
14 Abnormality diagnosis model for nuclear power plants using two-stage gated recurrent units
Kim, Jae Min;Lee, Gyumin;Lee, Changyong;Lee, Seung Jun; / Korean Nuclear Society , v.52, no.9, pp.2009-2016,
15 Robustness of optimized FPID controller against uncertainty and disturbance by fractional nonlinear model for research nuclear reactor
Zare, Nafiseh;Jahanfarnia, Gholamreza;Khorshidi, Abdollah;Soltani, Jamshid; / Korean Nuclear Society , v.52, no.9, pp.2017-2024,
16 Lab scale electrochemical codeposition experiments for comparison to computational predictions
Lafreniere, Philip;Zhang, Chao;Simpson, Michael;Blandford, Edward D.; / Korean Nuclear Society , v.52, no.9, pp.2025-2033,
17 Effect of irradiation on the oxidation kinetics of TODGA-based extraction mixtures at atmospheric pressure
Skvortsov, I.V.;Belova, E.V.;Yudintsev, S.V.; / Korean Nuclear Society , v.52, no.9, pp.2034-2040,
18 Understanding the role of hydrogen on creep behaviour of Zircaloy-4 cladding tubes using nanoindentation
Suman, Siddharth; / Korean Nuclear Society , v.52, no.9, pp.2041-2046,
19 Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
Suman, Siddharth; / Korean Nuclear Society , v.52, no.9, pp.2047-2053,
20 High-temperature oxidation behaviors of ZrSi2 and its coating on the surface of Zircaloy-4 tube by laser 3D printing
Kim, Jae Joon;Kim, Hyun Gil;Ryu, Ho Jin; / Korean Nuclear Society , v.52, no.9, pp.2054-2063,
21 Evaluation of the effect of mechanical deformation on beam isocenter properties of the SC200 scanning beam delivery system
Wang, Ming;Zheng, Jinxing;Song, Yuntao;Li, Ming;Zeng, Xianhu; / Korean Nuclear Society , v.52, no.9, pp.2064-2071,
22 Sensing changes in tumor during boron neutron capture therapy using PET with a collimator: Simulation study
Yang, Hye Jeong;Yoon, Do-Kun;Suh, Tae Suk; / Korean Nuclear Society , v.52, no.9, pp.2072-2077,
23 Physical and nuclear shielding properties of newly synthesized magnesium oxide and zinc oxide nanoparticles
Rashad, M.;Tekin, H.O.;Zakaly, Hesham MH.;Pyshkina, Mariia;Issa, Shams A.M.;Susoy, G.; / Korean Nuclear Society , v.52, no.9, pp.2078-2084,
24 External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, Korea
Lee, ChoongWie;Lee, Donghyun;Kim, Hee Reyoung;Lee, Seung Jun; / Korean Nuclear Society , v.52, no.9, pp.2085-2091,
25 The effect of crack length on SIF and elastic COD for elbow with circumferential through wall crack
Kim, Min Kyu;Jeon, Jun Hyeok;Choi, Jae Boong;Kim, Moon Ki; / Korean Nuclear Society , v.52, no.9, pp.2092-2099,
26 Analytic springback prediction in cylindrical tube bending for helical tube steam generator
Ahn, Kwanghyun;Lee, Kang-Heon;Lee, Jae-Seon;Won, Chanhee;Yoon, Jonghun; / Korean Nuclear Society , v.52, no.9, pp.2100-2106,
27 Performance analysis of S-CO2 recompression Brayton cycle based on turbomachinery detailed design
Zhang, Yuandong;Peng, Minjun;Xia, Genglei;Wang, Ge;Zhou, Cheng; / Korean Nuclear Society , v.52, no.9, pp.2107-2118,
28 Development of wall-thinning evaluation procedure for nuclear power plant piping - Part 2: Local wall-thinning estimation method
Yun, Hun;Moon, Seung-Jae;Oh, Young-Jin; / Korean Nuclear Society , v.52, no.9, pp.2119-2129,
29 A simple method for estimating the major nuclide fractional fission rates within light water and advanced gas cooled reactors
Mills, R.W.;Slingsby, B.M.;Coleman, J.;Collins, R.;Holt, G.;Metelko, C.;Schnellbach, Y.; / Korean Nuclear Society , v.52, no.9, pp.2130-2137,
30 Commissioning of neutron triple-axis spectrometers at HANARO
Hiraka, Haruhiro;Lee, Jisung;Jeon, Byoungil;Seong, Baek-Seok;Cho, Sangjin; / Korean Nuclear Society , v.52, no.9, pp.2138-2150,