American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 210 / Number 11

Volume 210

Number 11

Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models

Yongjae Kim, Seokhyeon Han, Seungjun Oh, Samwon Chung

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2009-2016

Review Article / dx.doi.org/10.1080/00295450.2024.2309599

Validation of EPG/SAG Rev. 4 of the Kuosheng Nuclear Power Plant Using the MAAP5 Code

Yu-Min Chen, Te-Chuan Wang, Min Lee

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2017-2037

Research Article / dx.doi.org/10.1080/00295450.2024.2306693

Estimation of Densities of Aqueous Actinide Solutions Ranging from Pure Water to Hydrated Crystals

Shekhar Kumar

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2038-2049

Research Article / dx.doi.org/10.1080/00295450.2024.2309070

Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly

Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2050-2073

Research Article / dx.doi.org/10.1080/00295450.2024.2309080

Effects of Impurities and Additives on Interactions of Nuclear-Grade Graphite with Molten LiF-NaF-KF

Krishna Moorthi Sankar, Preet M. Singh

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2074-2090

Research Article / dx.doi.org/10.1080/00295450.2024.2309600

A Blowdown Critical Heat Flux Experimental Vehicle

Musa Moussaoui, Wade Marcum

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2091-2114

Research Article / dx.doi.org/10.1080/00295450.2024.2309601

Creep Fatigue Analysis of the 316SS Monolith in the MegaPower Heat Pipe Reactor

Yong Wang, Lichuang Liang, Jun Tian, Dongchuan Su, Hui Li, Naibin Jiang

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2115-2132

Research Article / dx.doi.org/10.1080/00295450.2024.2310902

Development of Two-Step Method for Fast Chloride MSR Neutronics

Kyra Lawson, Nicholas R. Brown

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2133-2150

Research Article / dx.doi.org/10.1080/00295450.2024.2310911

Experimental Model to Study Characteristics of Radon Cover in Waste Landfills

Nora Nassiri-Mofakham, Mojtaba Kakaei

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2151-2158

Research Article / dx.doi.org/10.1080/00295450.2024.2311977

Optimization of Elliptical U-Tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method

Binqi Hao, He Zhou, Xiaofeng Li, Zu’An Wang, Shunyang Li, Pengfei Wang

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2159-2186

Research Article / dx.doi.org/10.1080/00295450.2024.2311978

Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels

Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2187-2203

Research Article / dx.doi.org/10.1080/00295450.2024.2312019

Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks

Ryan J. Hoover, Kenji Shimada

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2204-2214

Research Article / dx.doi.org/10.1080/00295450.2024.2312022

A Semi-Analytical Prediction Model for Fluid-Elastic Instability of a Normal Triangular Tube Array Under Transverse Flow Excitation

Gongbo Chen, Naibin Jiang

Nuclear Technology / Volume 210 / Number 11 / November 2024 / Pages 2215-2235

Research Article / dx.doi.org/10.1080/00295450.2024.2312023