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Volume 209

Number 7

Table of Contents

Condition Assessment of Nuclear Power Plant Equipment Based on Machine Learning Methods: A Review

Yong Xu, Yunze Cai, Lin Song

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 929-962

Critical Review / dx.doi.org/10.1080/00295450.2023.2169042

Oh, My Darling Clementine: A Detailed History and Data Repository of the Los Alamos Plutonium Fast Reactor

Hannah K. Patenaude, Franz J. Freibert

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 963-1007

Technical Paper / dx.doi.org/10.1080/00295450.2023.2176686

Evaluation of Sodium Radioactivity in the Primary System of the Prototype Fast Reactor Monju

Tetsuya Mouri, Kazuya Ohgama, Taira Hazama

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 1008-1023

Technical Paper / dx.doi.org/10.1080/00295450.2023.2181044

A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors

A. John Arul, Parthkumar Rajendrabhai Patel, Darpan Krishnakumar Shukla

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 1024-1039

Technical Paper / dx.doi.org/10.1080/00295450.2023.2175584

Design and Suitability Analysis of FPGA-Based TCP/IP Offload Module for Control Systems of FBRs

Aditya Gour, Tom Mathews, R. P. Behera

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 1040-1049

Technical Paper / dx.doi.org/10.1080/00295450.2023.2171664

Comprehensive Comparison of Nuclear Materials in BNPP Fuel Assemblies

Zahra Papi, Farrokh Khoshahval

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 1050-1067

Technical Paper / dx.doi.org/10.1080/00295450.2023.2167462

Safety Benefits Assessment for Accident Tolerant Fuels in Consideration of Steam Generator Tube Degradation Using Dynamic Event Tree Analysis

Jintae Kim, Asad Ullah Amin Shah, Hyun Gook Kang, Tunc Aldemir

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 1068-1085

Technical Paper / dx.doi.org/10.1080/00295450.2023.2171271

Numerical Simulation of Wall Condensation from a Superheated Steam and Air Mixture in a Vertical Pipe

Michio Murase, Yoichi Utanohara

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 1086-1100

Technical Paper / dx.doi.org/10.1080/00295450.2023.2175598

Treatment of Uranyl Nitrate Solution by Nanofiltration

Xiang Meng, Zhongwei Yuan, Taihong Yan, Weifang Zheng

Nuclear Technology / Volume 209 / Number 7 / July 2023 / Pages 1101-1107

Technical Paper / dx.doi.org/10.1080/00295450.2023.2169041

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