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Nuclear Engineering and Technology Volume 54, Issue 5, Pages 1535-1934 , May 2022

 

Original Articles Nuclear Fuel and Reactor Materials

 

Overview of CSNS tantalum cladded tungsten solid Target-1 and Target-2 Pages 1535-1540 Shaohong Wei, Ruiqiang Zhang, Quan Ji, Changfeng Li, Bin Zhou, Youlian Lu, Jun Xu, Ke Zhou, Chongguang Zhao, Ning He, Wen Yin, Tianjiao Liang

 

Effective thermal conductivity model of porous polycrystalline UO2: A computational approach Pages 1541-1548 Bohyun Yoon, Kunok Chang

 

Study of the mechanical properties and effects of particles for oxide dispersion strengthened Zircaloy-4 via a 3D representative volume element model Pages 1549-1559 Dong-Hyun Kim, Jong-Dae Hong, Hyochan Kim, Jaeyong Kim, Hak-Sung Kim

 

Effect of process parameters on the recovery of thorium tetrafluoride prepared by hydrofluorination of thorium oxide, and their optimization Pages 1560-1569 Raj Kumar, Sonal Gupta, Sourabh Wajhal, S.K. Satpati, M.L. Sahu

 

Creep strain modeling for alloy 690 SG tube material based on modified theta projection method Pages 1570-1578 Seongin Moon, Jong-Min Kim, Joon-Yeop Kwon, Bong-Sang Lee, Kwon-Jae Choi, Min-Chul Kim

 

Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations Pages 1579-1587 Shinhyo Bang, Ho-a Kim, Jae-soo Noh, Donguk Kim, Kyunghwan Keum, Youho Lee

 

Prediction of fatigue crack initiation life in SA312 Type 304LN austenitic stainless steel straight pipes with notch Pages 1588-1596 A. Ramachandra Murthy, S. Vishnuvardhan, K.V. Anjusha, P. Gandhi, P.K. Singh

 

Original Articles Nuclear Fuel Cycle and Radioactive Waste Management

 

Recovery of cesium ions from seawater using a porous silica-based ionic liquid impregnated adsorbent Pages 1597-1605 Hao Wu, Tatsuya Kudo, Seong-Yun Kim, Misako Miwa, Shigeo Matsuyama

 

Novel approach to predicting the release probability when applying the MARSSIM statistical test to a survey unit with a specific residual radioactivity distribution based on Monte Carlo simulation Pages 1606-1615 Ga Hyun Chun, Jae Hak Cheong

 

Sorption of Se(-II) on illite, MX-80 bentonite, shale, and limestone in Na–Ca–Cl solutions Pages 1616-1622 Andrew Walker, Joshua Racette, Takumi Saito, Tammy (Tianxiao) Yang, Shinya Nagasaki

 

Development of a gamma irradiation loop to evaluate the performance of a EURO-GANEX process Pages 1623-1634 I. Sánchez-García, H. Galán, A. Núñez, J.M. Perlado, J. Cobos

 

Original Articles Nuclear I&C

 

A formal approach to support the identification of unsafe control actions of STPA for nuclear protection systems Pages 1635-1643 Sejin Jung, Yoona Heo, Junbeom Yoo

 

Adaptive second-order nonsingular terminal sliding mode power-level control for nuclear power plants Pages 1644-1651 Jiuwu Hui, Jingqi Yuan

 

Experimental testing and evaluation of coating on cables in container fire test facility Pages 1652-1656 P. Babu Aurtherson, J. Hemanandh, Yuvarajan Devarajan, Ruby Mishra, Biju Cherian Abraham

 

Original Articles Nuclear Policy, Economics and Human Resource Development

 

Nuclear energy consumption and CO2 emissions in India: Evidence from Fourier ARDL bounds test approach Pages 1657-1663 Onder Ozgur, Veli Yilanci, Maxwell Kongkuah

 

Evaluating the asymmetric effects of nuclear energy on carbon emissions in Pakistan Pages 1664-1673 Muhammad Tariq Majeed, Ilhan Ozturk, Isma Samreen, Tania Luni

 

Original Articles Nuclear Safety

 

Transient simulation and experiment validation on the opening and closing process of a ball valve Pages 1674-1685 Yong Han, Ling Zhou, Ling Bai, Peng Xue, Wanning Lv, Weidong Shi, Gaoyang Huang

 

SACADA and HuREX: Part 1. the use of SACADA and HuREX systems to collect human reliability data Pages 1686-1697 Yung Hsien James Chang, Yochan Kim, Jinkyun Park, Lawrence Criscione

 

Application of a combined safety approach for the evaluation of safety margin during a Loss of Condenser Vacuum event Pages 1698-1711 Dong-Hun Shin, Hae-Yong Jeong, Moon-Ghu Park, Jung-Uk Sohn

 

Original Articles Nuclear Structural Analysis and Plant Management & Maintenance

 

Improvement on optimal design of dynamic absorber for enhancing seismic performance of nuclear piping using adaptive Kriging method Pages 1712-1725 Shinyoung Kwag, Seunghyun Eem, Jinsung Kwak, Hwanho Lee, Jinho Oh, Gyeong-Hoi Koo

 

Constraint-corrected fracture mechanics analysis of nozzle crotch corners in pressurized water reactors Pages 1726-1746 Jong-Sung Kim, Jun-Min Seo, Ju-Yeon Kang, Youn-Young Jang, Yun-Joo Lee, Kyu-Wan Kim

 

Original Articles Radiation Application

 

Application of a deep learning algorithm to Compton imaging of radioactive point sources with a single planar CdTe pixelated detector Pages 1747-1753 G. Daniel, Y. Gutierrez, O. Limousin

 

Source and LVis based coincidence summing correction in HPGe gamma-ray spectrometry Pages 1754-1759 Jieun Lee, HyoJin Kim, Yong Uk Kye, Dong Yeon Lee, Jeung Kee Kim, Wol Soon Jo, Yeong-Rok Kang

 

Improving light collection efficiency using partitioned light guide on pixelated scintillator-based γ-ray imager Pages 1760-1768 Suyeon Hyeon, Mark Hammig, Manhee Jeong

 

Original Articles Radiation Protection

 

Development of a dose estimation code for BNCT with GPU accelerated Monte Carlo and collapsed cone Convolution method Pages 1769-1780 Chang-Min Lee, Hee-Seock Lee

 

External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 1 Pages 1781-1788 Jihyang Byon, Sangjune Park, Yangjin Kim, Seokyoung Ahn

 

Original Articles Reactor Physics

 

Verification of a two-step code system MCS/RAST-F to fast reactor core analysis Pages 1789-1803 Tuan Quoc Tran, Alexey Cherezov, Xianan Du, Deokjung Lee

 

A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments Pages 1804-1812 A. Dokhane, A. Vasiliev, M. Hursin, D. Rochman, H. Ferroukhi

 

Verification of SARAX code system in the reactor core transient calculation based on the simplified EBR-II benchmark Pages 1813-1824 Xiaoqian Jia, Youqi Zheng, Xianna Du, Yongping Wang, Jianda Chen

 

Original Articles Thermal Hydraulics

 

Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles Pages 1825-1834 Huilun Kang, Zhaofei Tian, Guangliang Chen, Lei Li, Tianhui Chu

 

Cavitation optimization of single-orifice plate using CFD method and neighborhood cultivation genetic algorithm Pages 1835-1844 Yu Zhang, Jiang Lai, Chao He, Shihao Yang

 

Can a nanofluid enhance the critical heat flux if the recirculating coolant contains debris? Pages 1845-1850 Jihoon Han, Giju Nam, Hyungdae Kim

 

Experiment investigation on flow characteristics of open natural circulation system Pages 1851-1859 Xiangjie Qi, Zichen Zhao, Peng Ai, Peng Chen, Zhongning Sun, Zhaoming Meng

 

Comparative study of constitutive relations implemented in RELAP5 and TRACE – Part II: Wall boiling heat transfer Pages 1860-1873 Sung Gil Shin, Jeong Ik Lee

 

Evaluation of thermal-hydraulic performance and economics of Printed Circuit Heat Exchanger (PCHE) for recuperators of Sodium-cooled Fast Reactors (SFRs) using CO2 and N2 as working fluids Pages 1874-1889 Su Won Lee, Seong Min Shin, SungKun Chung, HangJin Jo

 

Development of a special thermal-hydraulic component model for the core makeup tank Pages 1890-1901 Min Gi Kim, Adnan Wisudhaputra, Jong-Hyuk Lee, Kyungdoo Kim, Hyun-Sik Park, Jae Jun Jeong

 

Technical Notes Reactor Physics

 

Performing linear regression with responses calculated using Monte Carlo transport codes Pages 1902-1908 Dean Price, Brendan Kochunas

 

Technical Notes Nuclear Fuel Cycle and Radioactive Waste Management

 

Uranium tetrafluoride production at pilot scale using a mercury electrode cell Pages 1909-1913 Munir Dides, José Hernández, Luis Olivares

 

Technical Notes Thermal Hydraulics

 

Numerical investigation of the critical heat flux in a 5 × 5 rod bundle with multi-grid Pages 1914-1928 Wei Liu, Zemin Shang, Shihao Yang, Lixin Yang, Zihao Tian, Yu Liu, Xi Chen, Qian Peng

 

Technical Notes Nuclear Fuel and Reactor Materials

 

On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation Pages 1929-1934 M. Romano, D. Pizzocri, L. Luzzi