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| 1 |
Evaluation of various large-scale energy storage technologies for flexible operation of existing pressurized water reactors
Heo, Jin Young;Park, Jung Hwan;Chae, Yong Jae;Oh, Seung Hwan;Lee, So Young;Lee, Ju Yeon;Gnanapragasam, Nirmal;Lee, Jeong Ik;
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Korean Nuclear Society
, v.53, no.8, pp.2427-2444,
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| 2 |
An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient
Kabach, Ouadie;Chetaine, Abdelouahed;Benchrif, Abdelfettah;Amsil, Hamid;
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Korean Nuclear Society
, v.53, no.8, pp.2445-2453,
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| 3 |
Use of americium as a burnable absorber for VVER-1200 reactor
Shelley, Afroza;Ovi, Mahmud Hasan;
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Korean Nuclear Society
, v.53, no.8, pp.2454-2463,
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| 4 |
Direct-contact heat transfer of single droplets in dispersed flow film boiling: Experiment and model assessment
Park, Junseok;Kim, Hyungdae;
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Korean Nuclear Society
, v.53, no.8, pp.2464-2476,
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| 5 |
Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility
Bae, Byoung-Uhn;Lee, Jae Bong;Park, Yu-Sun;Kim, Jongrok;Kang, Kyoung-Ho;
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Korean Nuclear Society
, v.53, no.8, pp.2477-2487,
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| 6 |
Multi-scale simulation of wall film condensation in the presence of non-condensable gases using heat structure-coupled CFD and system analysis codes
Lee, Chang Won;Yoo, Jin-Seong;Cho, Hyoung Kyu;
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Korean Nuclear Society
, v.53, no.8, pp.2488-2498,
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| 7 |
Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design
Bang, Jungjin;Jerng, Dong-Wook;Kim, Hangon;
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Korean Nuclear Society
, v.53, no.8, pp.2499-2508,
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| 8 |
A study on calculation of friction coefficient and packing stress using static diagnosis test for a balanced globe valve in nuclear power plants
Kim, Jaehyung;Lim, Taemook;Ryu, Ho-Geun;
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Korean Nuclear Society
, v.53, no.8, pp.2509-2522,
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| 9 |
Uncertainty quantification and propagation with probability boxes
Duran-Vinuesa, L.;Cuervo, D.;
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Korean Nuclear Society
, v.53, no.8, pp.2523-2533,
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| 10 |
Research on rapid source term estimation in nuclear accident emergency decision for pressurized water reactor based on Bayesian network
Wu, Guohua;Tong, Jiejuan;Zhang, Liguo;Yuan, Diping;Xiao, Yiqing;
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Korean Nuclear Society
, v.53, no.8, pp.2534-2546,
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| 11 |
Leak flow prediction during loss of coolant accidents using deep fuzzy neural networks
Park, Ji Hun;An, Ye Ji;Yoo, Kwae Hwan;Na, Man Gyun;
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Korean Nuclear Society
, v.53, no.8, pp.2547-2555,
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| 12 |
Control of a pressurized light-water nuclear reactor two-point kinetics model with the performance index-oriented PSO
Mousakazemi, Seyed Mohammad Hossein;
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Korean Nuclear Society
, v.53, no.8, pp.2556-2563,
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| 13 |
HCCR breeding blankets optimization by changing neutronic constrictions
Zadfathollah Seighalani, R.;Sedaghatizade, M.;Sadeghi, H.;
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Korean Nuclear Society
, v.53, no.8, pp.2564-2569,
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| 14 |
Hydrogen isotope exchange behavior of protonated lithium metal compounds
Park, Chan Woo;Kim, Sung-Wook;Sihn, Youngho;Yang, Hee-Man;Kim, Ilgook;Lee, Kwang Se;Roh, Changhyun;Yoon, In-Ho;
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Korean Nuclear Society
, v.53, no.8, pp.2570-2575,
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| 15 |
Evaluating thermal stability of rare-earth containing wasteforms at extraordinary nuclear disposal conditions
Kim, Miae;Hong, Kyong-Soo;Lee, Jaeyoung;Byeon, Mirang;Jeong, Yesul;Kim, Jong Hwa;Um, Wooyong;Kim, Hyun Gyu;
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Korean Nuclear Society
, v.53, no.8, pp.2576-2581,
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| 16 |
Effect of mechanical alloying on the microstructural evolution of a ferritic ODS steel with (Y-Ti-Al-Zr) addition processed by Spark Plasma Sintering (SPS)
Macia, E.;Garcia-Junceda, A.;Serrano, M.;Hong, S.J.;Campos, M.;
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Korean Nuclear Society
, v.53, no.8, pp.2582-2590,
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| 17 |
Effect of thermal aging on the mechanical, intergranular corrosion and corrosion fatigue properties of Z3CN20.09M cast duplex stainless steel
Ti, Wenxin;Wu, Huanchun;Xue, Fei;Zhang, Guodong;Peng, Qunjia;Fang, Kewei;Wang, Xitao;
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Korean Nuclear Society
, v.53, no.8, pp.2591-2599,
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| 18 |
Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel
Gao, Jun;Liu, Chang;Tan, Jibo;Zhang, Ziyu;Wu, Xinqiang;Han, En-Hou;Shen, Rui;Wang, Bingxi;Ke, Wei;
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Korean Nuclear Society
, v.53, no.8, pp.2600-2609,
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| 19 |
A study of predicting irradiation-induced transition temperature shift for RPV steels with XGBoost modeling
Xu, Chaoliang;Liu, Xiangbing;Wang, Hongke;Li, Yuanfei;Jia, Wenqing;Qian, Wangjie;Quan, Qiwei;Zhang, Huajian;Xue, Fei;
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Korean Nuclear Society
, v.53, no.8, pp.2610-2615,
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| 20 |
Modelling of effective irradiation swelling for inert matrix fuels
Zhang, Jing;Wang, Haoyu;Wei, Hongyang;Zhang, Jingyu;Tang, Changbing;Lu, Chuan;Huang, Chunlan;Ding, Shurong;Li, Yuanming;
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Korean Nuclear Society
, v.53, no.8, pp.2616-2628,
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| 21 |
Microstructural characteristics of a fresh U(Mo) monolithic mini-plate: Focus on the Zr coating deposited by PVD
Iltis, Xaviere;Drouan, Doris;Blay, Thierry;Zacharie, Isabelle;Sabathier, Catherine;Onofri, Claire;Steyer, Christian;Schwarz, Christian;Baumeister, Bruno;Allenou, Jerome;Stepnik, Bertrand;Petry, Winfried;
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Korean Nuclear Society
, v.53, no.8, pp.2629-2639,
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| 22 |
Development and performance evaluation of large-area hybrid gamma imager (LAHGI)
Lee, Hyun Su;Kim, Jae Hyeon;Lee, Junyoung;Kim, Chan Hyeong;
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Korean Nuclear Society
, v.53, no.8, pp.2640-2645,
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| 23 |
Performance evaluation of an adjustable gantry PET (AGPET) for small animal PET imaging
Song, Hankyeol;Kang, In Soo;Kim, Kyu Bom;Park, Chanwoo;Baek, Min Kyu;Lee, Seongyeon;Chung, Yong Hyun;
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Korean Nuclear Society
, v.53, no.8, pp.2646-2651,
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| 24 |
Region-wise evaluation of gamma-ray exposure dose in decontamination operation after a nuclear accident
Jeong, Hae Sun;Hwang, Won Tae;Han, Moon Hee;Kim, Eun Han;Lee, Jo Eun;Lee, Cheol Woo;
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Korean Nuclear Society
, v.53, no.8, pp.2652-2660,
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| 25 |
Gamma ray exposure buildup factor and shielding features for some binary alloys using MCNP-5 simulation code
Rammah, Y.S.;Mahmoud, K.A.;Mohammed, Faras Q.;Sayyed, M.I.;Tashlykov, O.L.;El-Mallawany, R.;
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Korean Nuclear Society
, v.53, no.8, pp.2661-2668,
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| 26 |
Investigation on cavitating flow and parameter effects in a control valve with a perforated cage
Wang, Hong;Zhu, Zhimao;Zhang, Miao;Li, Jie;Huo, Weiqi;
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Korean Nuclear Society
, v.53, no.8, pp.2669-2681,
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| 27 |
Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation
Li, Z.C.;Yang, Y.H.;Dong, Z.F.;Huang, T.;Wu, H.;
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Korean Nuclear Society
, v.53, no.8, pp.2682-2695,
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| 28 |
Efficiency of various structural modeling schemes on evaluating seismic performance and fragility of APR1400 containment building
Nguyen, Duy-Duan;Thusa, Bidhek;Park, Hyosang;Azad, Md Samdani;Lee, Tae-Hyung;
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Korean Nuclear Society
, v.53, no.8, pp.2696-2707,
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| 29 |
Position error compensation of the multi-purpose overload robot in nuclear power plants
Qin, Guodong;Ji, Aihong;Cheng, Yong;Zhao, Wenlong;Pan, Hongtao;Shi, Shanshuang;Song, Yuntao;
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Korean Nuclear Society
, v.53, no.8, pp.2708-2715,
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| 30 |
Earthquake response of a core shroud for APR1400
Jhung, Myung Jo;Choi, Youngin;Oh, Chang-Sik;
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Korean Nuclear Society
, v.53, no.8, pp.2716-2727,
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| 31 |
Mitigation of seismic responses of actual nuclear piping by a newly developed tuned mass damper device
Kwag, Shinyoung;Eem, Seunghyun;Kwak, Jinsung;Lee, Hwanho;Oh, Jinho;Koo, Gyeong-Hoi;
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Korean Nuclear Society
, v.53, no.8, pp.2728-2745,
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| 32 |
Testing the pollution haven hypothesis on the pathway of sustainable development: Accounting the role of nuclear energy consumption
Danish, Danish;Ud-Din Khan, Salah;Ahmad, Ashfaq;
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Korean Nuclear Society
, v.53, no.8, pp.2746-2752,
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| 33 |
Exergy and exergoeconomic analysis of hydrogen and power cogeneration using an HTR plant
Norouzi, Nima;Talebi, Saeed;Fani, Maryam;Khajehpour, Hossein;
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Korean Nuclear Society
, v.53, no.8, pp.2753-2760,
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| 34 |
Selection of a carrying agent for obtaining radioactive methyliodide vapors under dynamic conditions
Obruchikov, Alexander V.;Merkushkin, Aleksei O.;Magomedbekov, Eldar P.;Anurova, Olga M.;Vanina, Elena A.;
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Korean Nuclear Society
, v.53, no.8, pp.2761-2766,
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| 35 |
Bragg-curve simulation of carbon-ion beams for particle-therapy applications: A study with the GEANT4 toolkit
Hamad, Morad Kh.;
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Korean Nuclear Society
, v.53, no.8, pp.2767-2773,
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