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Nuclear Engineering and Technology  

논문
1 Review of the regulatory periodic inspection system from the viewpoint of defense-in-depth in nuclear safety
Lim, Jihan;Kim, Hyungjin;Park, Younwon; / Korean Nuclear Society , v.50, no.7, pp.997-1005,
2 Radiation detector deadtime and pile up: A review of the status of science
Usman, Shoaib;Patil, Amol; / Korean Nuclear Society , v.50, no.7, pp.1006-1016,
3 Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
Torabi, Mina;Lashkari, A.;Masoudi, Seyed Farhad;Bagheri, Somayeh; / Korean Nuclear Society , v.50, no.7, pp.1017-1023,
4 Criticality benchmark of McCARD Monte Carlo code for light-water-reactor fuel in transportation and storage packages
Jang, Junkyung;Lee, Hochul;Lee, Hyun Chul; / Korean Nuclear Society , v.50, no.7, pp.1024-1036,
5 Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life
Ahmadi, M.;Pirouzmand, A.;Rabiee, A.; / Korean Nuclear Society , v.50, no.7, pp.1037-1042,
6 Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD
Park, Ho Jin;Lee, Dong Hyuk;Jeon, Byoung Kyu;Shim, Hyung Jin; / Korean Nuclear Society , v.50, no.7, pp.1043-1050,
7 Kinetics calculation of fast periodic pulsed reactors using MCNP6
Zhon, Z.;Gohar, Y.;Talamo, A.;Cao, Y.;Bolshinsky, I.;Pepelyshev, Yu N.;Vinogradov, Alexander; / Korean Nuclear Society , v.50, no.7, pp.1051-1059,
8 Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system
Hong, Seong Hee;Kim, Myung Hyun; / Korean Nuclear Society , v.50, no.7, pp.1060-1067,
9 Experimental study of bubble behaviors and CHF on printed circuit board (PCB) in saturated pool water at various inclination angles
Tanjung, Elvira F.;Alunda, Bernard O.;Lee, Yong Joong;Jo, Daeseong; / Korean Nuclear Society , v.50, no.7, pp.1068-1078,
10 Research on flow characteristics in supercritical water natural circulation: Influence of heating power distribution
Ma, Dongliang;Zhou, Tao;Feng, Xiang;Huang, Yanping; / Korean Nuclear Society , v.50, no.7, pp.1079-1087,
11 A study on characteristics and internal exposure evaluation of radioactive aerosols during pipe cutting in decommissioning of nuclear power plant
Kim, Sun Il;Lee, Hak Yun;Song, Jong Soon; / Korean Nuclear Society , v.50, no.7, pp.1088-1098,
12 How should the regulatory defaults be set?
Jang, Seung-Cheol; / Korean Nuclear Society , v.50, no.7, pp.1099-1105,
13 Study on resonant electron cyclotron heating by OSXB double mode conversion at the W7-X stellarator
Adlparvar, S.;Miraboutalebi, S.;Kiai, S.M. Sadat;Rajaee, L.; / Korean Nuclear Society , v.50, no.7, pp.1106-1111,
14 Highly efficient adsorptive removal of uranyl ions from aqueous solutions using dicalcium phosphate nanoparticles as a superabsorbent
Saghatchi, Hadis;Ansari, Reza;Mousavi, H. Zavvar; / Korean Nuclear Society , v.50, no.7, pp.1112-1119,
15 Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards
Woo, Seung Min;Chirayath, Sunil S.;Fratoni, Massimiliano; / Korean Nuclear Society , v.50, no.7, pp.1120-1130,
16 Effect of serrated grain boundary on stress corrosion cracking of Alloy 600
Kim, H.P.;Choi, M.J.;Kim, S.W.;Kim, D.J.;Lim, Y.S.;Hwang, S.S.; / Korean Nuclear Society , v.50, no.7, pp.1131-1137,
17 Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses
Zhang, Jingyu;Zhu, Jiacheng;Ding, Shurong;Chen, Liang;Li, Wenjie;Pang, Hua; / Korean Nuclear Society , v.50, no.7, pp.1138-1147,
18 Experimental simulation of activity release from leaking fuel rods
Somfai, Barbara;Hozer, Zoltan;Nagy, Imre; / Korean Nuclear Society , v.50, no.7, pp.1148-1153,
19 Precise prediction of radiation interaction position in plastic rod scintillators using a fast and simple technique: Artificial neural network
Peyvandi, R. Gholipour;rad, S.Z. Islami; / Korean Nuclear Society , v.50, no.7, pp.1154-1159,
20 Detectability evaluation of the loose parts in steam generator by eddy current testing techniques
Kim, Kyungcho;Min, Kyongmahn;Kim, Changkuen;Kim, Jin-Gyum;Jhung, Myungjo; / Korean Nuclear Society , v.50, no.7, pp.1160-1167,
21 Development of the nuclear safety trust indicator
Cho, SeongKyung; / Korean Nuclear Society , v.50, no.7, pp.1168-1172,
22 Numerical prediction of a flashing flow of saturated water at high pressure
Jo, Jong Chull;Jeong, Jae Jun;Yun, Byong Jo;Moody, Frederick J.; / Korean Nuclear Society , v.50, no.7, pp.1173-1183,
23 Residual salt separation technique using centrifugal force for pyroprocessing
Kim, Sung-Wook;Lee, Jong Kwang;Ryu, Dongseok;Jeon, Min Ku;Hong, Sun-Seok;Heo, Dong Hyun;Choi, Eun-Young; / Korean Nuclear Society , v.50, no.7, pp.1184-1189,
24 Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
Khvostov, Grigori; / Korean Nuclear Society , v.50, no.7, pp.1190-1197,