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Nuclear Engineering and Technology Volume 53, Issue 3, Pages 699-1048 , March 2021

 

Review Article Thermal Hydraulics

 

Recent trends of supercritical CO2 Brayton cycle: Bibliometric analysis and research review Pages 699-714 Aofang Yu, Wen Su, Xinxing Lin, Naijun Zhou

 

Original Articles Reactor Physics

 

Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters Pages 715-731 Bamidele Ebiwonjumi, Chidong Kong, Peng Zhang, Alexey Cherezov, Deokjung Lee

 

On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX Pages 732-740 Bowen Xiao, Linfang Wei, Youqi Zheng, Bin Zhang, Hongchun Wu

 

Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS Pages 741-751 A. Pourrostam, S. Talebi, O. Safarzadeh

 

Original Articles Thermal Hydraulics

 

Numerical simulation on LMR molten-core centralized sloshing benchmark experiment using multi-phase smoothed particle hydrodynamics Pages 752-762 Young Beom Jo, So-Hyun Park, Juryong Park, Eung Soo Kim

 

The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT Pages 763-775 Xiaohan Zhao, Mingjun Wang, Ge Wu, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su

 

Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform Pages 776-792 Kyung Mo Kim, In Cheol Bang

 

Scaling analysis of the pressure suppression containment test facility for the small pressurized water reactor Pages 793-803 Xinxing Liu, Xiangjie Qi, Nan Zhang, Zhaoming Meng, Zhongning Sun

 

Model of the onset of liquid entrainment in large branch T-junction with the consideration of surface tension Pages 804-811 Ping Liu, Geyu Shen, Xiaoyu Li, Jinchen Gao, Zhaoming Meng

 

Original Articles Nuclear Safety

 

Analysis of fission product reduction strategy in SGTR accident using CFVS Pages 812-824 Hoyoung Shin, Seungwoo Kim, Yerim Park, Youngho Jin, Dong Ha Kim, Moosung Jae

 

Perception-based analytical technique of evacuation behavior under radiological emergency: An illustration of the Kori area Pages 825-832 Jeongsik Kim, Byoung-Jik Kim, Namhun Kim

 

MPS eutectic reaction model development for severe accident phenomenon simulation Pages 833-841 Yingzi Zhu, Jinbiao Xiong, Yanhua Yang

 

Original Articles Nuclear I&C

 

Applications of online simulation supporting PWR operations Pages 842-850 Chunbing Wang, Qizhi Duan, Chao Zhang, Yipeng Fan

 

Design of the flexible switching controller for small PWR core power control with the multi-model Pages 851-859 Wenjie Zeng, Qingfeng Jiang, Shangmian Du, Tianyu Hui, Yinuo Liu, Sha Li

 

Quantification of predicted uncertainty for a data-based model Pages 860-865 Jangbom Chai, Taeyun Kim

 

Syntactic and semantic information extraction from NPP procedures utilizing natural language processing integrated with rules Pages 866-878 Yongsun Choi, Minh Duc Nguyen, Thomas N. Kerr

 

A novel approach for analyzing the nuclear supply chain cyber-attack surface Pages 879-887 Shannon Eggers

 

Development of de-noised image reconstruction technique using Convolutional AutoEncoder for fast monitoring of fuel assemblies Pages 888-893 Se Hwan Choi, Hyun Joon Choi, Chul Hee Min, Young Hyun Chung, Jae Joon Ahn

 

Original Articles Nuclear Fuel Cycle and Radioactive Waste Management

 

Sorption of Pd on illite, MX-80 bentonite and shale in Na–Ca–Cl solutions Pages 894-900 Jared Goguen, Andrew Walker, Joshua Racette, Justin Riddoch, Shinya Nagasaki

 

Original Articles Nuclear Fuel and Reactor Materials

 

Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method Pages 901-910 Eun-ki Lee

 

Establishment of the design stress intensity value for the plate-type fuel assembly using a tensile test Pages 911-919 Hyun-Jung Kim, Young-Wook Tahk, Hyunwoo Jun, Eui-Hyun Kong, Jae-Yong Oh, Jeong-Sik Yim

 

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt Pages 920-926 N. Dianne Bull Ezell, Stephen S. Raiman, J. Matt Kurley, Joel McDuffee

 

Electrochemical corrosion study of helium ions implanted Zircaloy-4 in chloride media Pages 927-931 Mohsin Rafique, Atika Khan, Naveed Afzal, Ameeq Farooq, M. Imran

 

Fracture simulation of SFR metallic fuel pin using finite element damage analysis method Pages 932-941 Hyun-Woo Jung, Hyun-Kyu Song, Yun-Jae Kim, Dong-Wook Jerng

 

Original Articles Radiation Application

 

Determining PGAA collimator plug design using Monte Carlo simulation Pages 942-948 A. Jalil, A. Chetaine, H. Amsil, K. Embarch, A. Benchrif, K. Laraki, H. Marah

 

Original Articles Radiation Protection

 

Investigation of photon, neutron and proton shielding features of H3BO3–ZnO–Na2O–BaO glass system Pages 949-959 M.H.A. Mhareb, Y.S.M. Alajerami, Nidal Dwaikat, M.S. Al-Buriahi, Muna Alqahtani, Fatimh Alshahri, Noha Saleh, N. Alonizan, M.A. Saleh, M.I. Sayyed

 

Estimation of radiostrontium, radiocesium and radiobarium transfer from arid soil to plant: A case study from Kuwait Pages 960-966 Abdulaziz Aba, Anfal Ismaeel, Omar Al-Boloushi

 

Original Articles Nuclear Structural Analysis and Plant Management & Maintenance

 

Methodology of seismic-response-correlation-coefficient calculation for seismic probabilistic safety assessment of multi-unit nuclear power plants Pages 967-973 Seunghyun Eem, In-Kil Choi, Beomjoo Yang, Shinyoung Kwag

 

Application of cohesive zone model to large scale circumferential through-wall and 360° surface cracked pipes under static and dynamic loadings Pages 974-987 Ji-Hee Moon, Youn-Young Jang, Nam-Su Huh, Do-Jun Shim, Kyoungsoo Park

 

Investigation of seismic responses of reactor vessel and internals for beyond-design basis earthquake using elasto-plastic time history analysis Pages 988-1003 Sang-Jeong Lee, Eun-ho Lee, Changkyun Lee, No-Cheol Park, Youngin Choi, Changsik Oh

 

Finite element analysis of high-density polyethylene pipe in pipe gallery of nuclear power plants Pages 1004-1012 Jianfeng Shi, Anqi Hu, Fa Yu, Ying Cui, Ruobing Yang, Jinyang Zheng

 

Original Articles Nuclear Policy, Economics and Human Resource Development

 

Sentiment analysis of nuclear energy-related articles and their comments on a portal site in Rep. of Korea in 2010–2019 Pages 1013-1019 So Yun Jeong, Jae Wook Kim, Young Seo Kim, Han Young Joo, Joo Hyun Moon

 

Technical Notes Thermal Hydraulics

 

Research on non-uniform pressure pulsation of the diffuser in a nuclear reactor coolant pump Pages 1020-1028 Qiang Zhou, Hongkun Li, Lin Pei, Zuowen Zhong

 

Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break Pages 1029-1040 Jong Chull Jo, Jae-Jun Jeong, Frederick J. Moody

 

Technical Notes Nuclear Fuel Cycle and Radioactive Waste Management

 

Measuring thermal conductivity and water suction for variably saturated bentonite Pages 1041-1048 Seok Yoon, Geon-Young Kim