Nuclear Engineering and Technology Volume 52, Issue 12, Pages 2687-2982 , December 2020

 

Review Article Nuclear I&C

 

A new perspective towards the development of robust data-driven intrusion detection for industrial control systems Pages 2687-2698 Abiodun Ayodeji, Yong-kuo Liu, Nan Chao, Li-qun Yang

 

OriginalArticles Reactor Physics

 

Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator Pages 2699-2708 Ahmed Amin E. Abdelhameed, Khurrum Saleem Chaudri, Yonghee Kim

 

Application of deep neural networks for high-dimensional large BWR core neutronics Pages 2709-2716 Rabie Abu Saleem, Majdi I. Radaideh, Tomasz Kozlowski

 

Comprehensive validation of silicon cross sections Pages 2717-2724 Tomáš Czakoj, Michal Košťál, Jan Šimon, Jaroslav Šoltés, Martin Mareček, Roberto Capote

 

Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library Pages 2725-2732 Donny Hartanto, Peng Hong Liem

 

An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis Pages 2733-2742 Ching-Sheng Lin, Won Sik Yang

 

Thermal Hydraulics

 

Conceptual design of small modular reactor driven by natural circulation and study of design characteristics using CFD & RELAP5 code Pages 2743-2759 Mun Soo Kim, Yong Hoon Jeong

 

Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon Pages 2760-2770 Alok Jha, Anurag Gupta, Rajarshi Das, Shantanu D. Paraswar

 

Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution Pages 2771-2788 Omar S. Al-Yahia, Ho Joon Yoon, Daeseong Jo

 

Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor Pages 2789-2802 Pengcheng Zhao, Zijing Liu, Tao Yu, Jinsen Xie, Zhenping Chen, Chong Shen

 

CFD study of the PTS experiment in ROCOM test facility Pages 2803-2811 Zoran Čarija, Fran Ledić, Ante Sikirica, Bojan Niceno

 

Nuclear Safety

 

Effects of house load operation on PSA based on operational experiences in Korea Pages 2812-2820 Hak Kyu Lim, Jong-hoon Park

 

Parameter importance ranking for SBLOCA of CPR1000 with moment-independent sensitivity analysis Pages 2821-2835 Qingwen Xiong, Junli Gou, Jianqiang Shan

 

Improved prediction model for H2/CO combustion risk using a calculated non-adiabatic flame temperature model Pages 2836-2846 Yeon Soo Kim, Joongoo Jeon, Chang Hyun Song, Sung Joong Kim

 

Nuclear I&C

 

On-site water level measurement method based on wavelength division multiplexing for harsh environments in nuclear power plants Pages 2847-2851 Hoon-Keun Lee, Jaeyul Choo, Gangsig Shin, Sung-Man Kim

 

Simulation, design optimization, and experimental validation of a silver SPND for neutron flux mapping in the Tehran MTR Pages 2852-2859 Mahdi Saghafi, Seyed Mohsen Ayyoubzadeh, Mohammad Sadegh Terman

 

Nuclear Physics, Fusion, and Laser Technology

 

Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation Pages 2860-2866 Xiao-Yu Ding, Qiu Xu, Xiao-yong Zhu, Lai-Ma Luo, Jian-Jun Huang, Bin Yu, Xiang Gao, Jian-Gang Li, Yu-Cheng Wu

 

Nuclear Fuel Cycle and Radioactive Waste Management

 

Restoration of the isotopic composition of reprocessed uranium hexafluoride using cascade with additional product Pages 2867-2873 Valerii Palkin, Eugenii Maslyukov

 

Novel homogeneous burnable poisons in pressurized water reactor ceramic fuel Pages 2874-2879 Brandon Dodd, Taylor Britt, Cody Lloyd, Manit Shah, Braden Goddard

 

Nuclear Fuel and Reactor Materials

 

Thermodynamic and experimental analyses of the oxidation behavior of UO2 pellets in damaged fuel rods of pressurized water reactors Pages 2880-2886 Tae-Sik Jung, Yeon-Soo Na, Min-Jae Joo, Kwang-Young Lim, Yoon-Ho Kim, Seung-Jae Lee

 

Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code Pages 2887-2900 G. Khvostov

 

Thermal creep behavior of CZ cladding under biaxial stress state Pages 2901-2909 Jin Xin, Lin Yuyu, Zhang Libin

 

Radiation Application

 

Performance of 3D printed plastic scintillators for gamma-ray detection Pages 2910-2917 Dong-geon Kim, Sangmin Lee, Junesic Park, Jaebum Son, Tae Hoon Kim, Yong Hyun Kim, Kihong Pak, Yong Kyun Kim

 

Nuclear Structural Analysis and Plant Management & Maintenance

 

Simplified elastic-plastic analysis procedure for strain-based fatigue assessment of nuclear safety class 1 components under severe seismic loads Pages 2918-2927 Jong-Sung Kim, Jun-Young Kim

 

Entropy and exergy analysis and optimization of the VVER nuclear power plant with a capacity of 1000 MW using the firefly optimization algorithm Pages 2928-2938 Saeed Talebi, Nima Norouzi

 

Analytic responses of slender beams supported by rotationally restrained hinges during support motions Pages 2939-2948 Jeong Yeon Ryu, Yong-Woo Kim

 

Crack growth analysis and remaining life prediction of dissimilar metal pipe weld joint with circumferential crack under cyclic loading Pages 2949-2957 A. Ramachandra Murthy, P. Gandhi, S. Vishnuvardhan, G. Sudharshan

 

Nuclear Policy, Economics and Human Resource Development

 

Analyzing local perceptions toward the new nuclear research reactor in Thailand Pages 2958-2968 Sarasinee Tantitaechochart, Naraphorn Paoprasert, Kampanart Silva

 

Is nuclear energy a better alternative for mitigating CO2 emissions in BRICS countries? An empirical analysis Pages 2969-2974 Syed Tauseef Hassan, Danish, Salah-Ud-Din khan, Muhammad Awais Baloch, Zahid Hassan Tarar

 

Technical Note Nuclear Structural Analysis and Plant Management & Maintenance

 

Evaluation of the radiation damage effect on mechanical properties in Tehran research reactor (TRR) clad Pages 2975-2981 Mohamad Amin Amirkhani, Farrokh Khoshahval