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Volume 207

Number 4

Table of Contents

Transient System Thermal-Hydraulic Assessment of Advanced Uranium- and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors—I: Two-Channel Analyses

S. Wang, T. Beuthe, X. Huang, A. Nava Dominguez, A. V. Colton, B. P. Bromley

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 469-493

Technical Paper / dx.doi.org/10.1080/00295450.2020.1788302

Transient System Thermal-Hydraulic Assessment of Advanced Uranium- and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors—II: Full-Core Analyses

S. Wang, T. Beuthe, X. Huang, A. Nava Dominguez, B. P. Bromley, A. V. Colton

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 494-520

Technical Paper / dx.doi.org/10.1080/00295450.2020.1784669

Development of the NuScale Power Module in the INL Modelica Ecosystem

Konor Frick, Shannon Bragg-Sitton

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 521-542

Technical Paper / dx.doi.org/10.1080/00295450.2020.1781497

Nuclear Air-Brayton Power Cycles with Thermodynamic Topping Cycles, Assured Peaking Capacity, and Heat Storage for Variable Electricity and Heat

Charles W. Forsberg, Patrick J. McDaniel, Bahman Zohuri

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 543-557

Technical Paper / dx.doi.org/10.1080/00295450.2020.1785793

Pattern Recognition–Based Technique for Control Rod Position Identification in Pressurized Water Reactors

Mohamed Elsamahy, Tarek F. Nagla, Mohamed A. E. Abdel-Rahman

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 558-574

Technical Paper / dx.doi.org/10.1080/00295450.2020.1792742

Quantitative Evaluation on the Effect of Experience Under Emergency Situations in NPP Main Control Room Based on Multimodal Data

Zhiyao Liu, Qichao Zhao, Liming Zhang, Xuegang Zhang, Jieyun Fan, Qingju Wang, Ping Wu

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 575-581

Technical Paper / dx.doi.org/10.1080/00295450.2020.1784683

Impact of Radial Reflector Fidelity on Neutronics and Vessel Fluence Simulations

S. Stimpson, T. Pandya, K. Royston, B. Collins, A. Godfrey

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 582-595

Technical Paper / dx.doi.org/10.1080/00295450.2020.1770557

Gross Alpha-Based Continuous Air Monitor: Mathematical Modeling, Measurements, and Interpretation

Tanmoy Das, R. V. Kolekar, R. K. Gopalakrishnan

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 596-603

Technical Paper / dx.doi.org/10.1080/00295450.2020.1792754

Transmission of Images on High-Temperature Nuclear-Grade Metallic Pipe with Ultrasonic Elastic Waves

A. Heifetz, D. Shribak, X. Huang, B. Wang, J. Saniie, R. Ponciroli, E. R. Koehl, S. Bakhtiari, R. B. Vilim

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 604-616

Technical Paper / dx.doi.org/10.1080/00295450.2020.1782626

Electrochemical and Laser-Induced Breakdown Spectroscopy Signal Fusion for Detection of UCl₃-GdCl₃-MgCl₂ in LiCl-KCl Molten Salt

H. Andrews, S. Phongikaroon

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 617-626

Technical Paper / dx.doi.org/10.1080/00295450.2020.1776538

A Rigorous Method for Selecting the Most Limiting Exposure During Cycle for Anticipated Transient Without SCRAM with Instability Analysis

Peter Yarsky, Andrew Bielen

Nuclear Technology / Volume 207 / Number 4 / April 2021 / Pages 627-635

Technical Note / dx.doi.org/10.1080/00295450.2020.1774260

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