ANS / Publications / Journals / Nuclear Technology

Yanzi Liu, Xuegang Zhang, Gang Zhang, Jianjun Jiang, Li Zhang, Hong Hu, Tao Qing, Yanhua Zou, Dan Yang, Liaozi Xi, Fan Tang, Ming Jia, Yiqian Wu, Zhiyao Liu

Nuclear Technology / Volume 207 / Number 1 / January 2021 / Pages 74-93

Technical Paper / dx.doi.org/10.1080/00295450.2020.1733376

Comparison of Analysis Results on Three Methods for Sampling Crud, a Radioactive Corrosion Product with Zinc-Injected Spent PWR Nuclear Fuel Rods

Yang Hong Jung, Seung Je Baik, Young Gwan Jin

Nuclear Technology / Volume 207 / Number 1 / January 2021 / Pages 94-102

Technical Paper / dx.doi.org/10.1080/00295450.2020.1738795

Airborne Release Fractions from Surrogate Nuclear Waste Fires Containing Lanthanide Nitrates and Depleted Uranium Nitrate in 30% Tributyl Phosphate in Kerosene

Joshua A. Hubbard, Timothy J. Boyle, Ethan T. Zepper, Alexander Brown, Taylor Settecerri, Joshua L. Santarpia, Paul Kotula, Bonnie McKenzie, Gabriel A. Lucero, Laura J. Lemieux, Joseph A. Zigmond, Nicole D. Zayas, Rose Preston, Brenda Maes, Andres L. Sanchez, Dora K. Wiemann, Fernando Guerrero, Xavier J. Robinson, Dianna Perales

Nuclear Technology / Volume 207 / Number 1 / January 2021 / Pages 103-118

Technical Paper / dx.doi.org/10.1080/00295450.2020.1739995

Redox Behavior of Moisture in LiCl-KCl Eutectic Melts: A Cyclic Voltammetry Study

Litun Swain, Suddhasattwa Ghosh, Gurudas Pakhui, Bandi Prabhakara Reddy

Nuclear Technology / Volume 207 / Number 1 / January 2021 / Pages 119-146

Technical Paper / dx.doi.org/10.1080/00295450.2020.1743101

X-Ray and Neutron Radiography System Optimization by Means of a Multiobjective Approach and a Simplified Ray-Tracing Method

Robert Nshimirimana, Ajith Abraham, Gawie Nothnagel, Andries Engelbrecht

Nuclear Technology / Volume 207 / Number 1 / January 2021 / Pages 147-166

Technical Paper / dx.doi.org/10.1080/00295450.2020.1740562

Thirty Minutes Before the Dawn

Alan B. Carr

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S1-S23

Critical Review / dx.doi.org/10.1080/00295450.2021.1927625

Nuclear Science for the Manhattan Project and Comparison to Today’s ENDF Data

Mark B. Chadwick

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S24-S61

Critical Review / dx.doi.org/10.1080/00295450.2021.1901002

Criticality Experiments with Fast ²³⁵U and ²³⁹Pu Metal and Hydride Systems During the Manhattan Project

Jesson Hutchinson, Jennifer Alwin, Alexander McSpaden, William Myers, Michael Rising, Rene Sanchez

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S62-S80

Technical Paper / dx.doi.org/10.1080/00295450.2021.1908076

Critical Assemblies: Dragon Burst Assembly and Solution Assemblies

Robert Kimpland, Travis Grove, Peter Jaegers, Richard Malenfant, William Myers

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S81-S99

Critical Review / dx.doi.org/10.1080/00295450.2021.1927626

Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo

Avneet Sood, R. Arthur Forster, B. J. Archer, R. C. Little

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S100-S133

Critical Review / dx.doi.org/10.1080/00295450.2021.1956255

Canadian Contributions to the Manhattan Project and Early Nuclear Research

Stephen A. Andrews, Madison T. Andrews, Thomas E. Mason

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S134-S146

Critical Review / dx.doi.org/10.1080/00295450.2021.1913033

On the Origins of Lagrangian Hydrodynamic Methods

Nathaniel R. Morgan, Billy J. Archer

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S147-S175

Technical Paper / dx.doi.org/10.1080/00295450.2021.1913034

Trinity by the Numbers: The Computing Effort that Made Trinity Possible

N. Lewis

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S176-S189

Critical Review / dx.doi.org/10.1080/00295450.2021.1938487

The Los Alamos Computing Facility During the Manhattan Project

B. J. Archer

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S190-S203

Technical Paper / dx.doi.org/10.1080/00295450.2021.1940060

The Trinity High-Explosive Implosion System: The Foundation for Precision Explosive Applications

Eric N. Brown, Dan L. Borovina

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S204-S221

Critical Review / dx.doi.org/10.1080/00295450.2021.1913954

Woolwich, Bruceton, Los Alamos: Munroe Jets and the Trinity Gadget

Richard Moore, Eric N. Brown

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S222-S230

Technical Paper / dx.doi.org/10.1080/00295450.2021.1905463

The Origins of Blast-Loaded Vessels

Jonathan E. Morgan

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S231-S265

Critical Review / dx.doi.org/10.1080/00295450.2021.1909371

The Taming of Plutonium: Plutonium Metallurgy and the Manhattan Project

Joseph C. Martz, Franz J. Freibert, David L. Clark

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S266-S285

Technical Paper / dx.doi.org/10.1080/00295450.2021.1913035

Equation of State: Manhattan Project Developments and Beyond

Scott D. Crockett, Franz J. Freibert

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S286-S294

Technical Note / dx.doi.org/10.1080/00295450.2021.1913036

Weapons Radiochemistry: Trinity and Beyond

Susan K. Hanson, Warren J. Oldham

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S295-S308

Critical Review / dx.doi.org/10.1080/00295450.2021.1951538

Gamma and Decay Energy Spectroscopy Measurements of Trinitite

David J. Mercer, Katrina E. Koehler, Mark P. Croce, Andrew S. Hoover, Philip A. Hypes, Stosh A. Kozimor, Veronika Mocko, Paul R. J. Saey, Daniel R. Schmidt, Joel N. Ullom

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S309-S320

Technical Note / dx.doi.org/10.1080/00295450.2021.1922258

A New Yield Assessment for the Trinity Nuclear Test, 75 Years Later

Hugh D. Selby, Susan K. Hanson, Daniel Meininger, Warren J. Oldham, William S. Kinman, Jeffrey L. Miller, Sean D. Reilly, Allison M. Wende, Jennifer L. Berger, Jeremy Inglis, Anthony D. Pollington, Christopher R. Waidmann, Roger A. Meade, Kevin L. Buescher, James R. Gattiker, Scott A. Vander Wiel, Peter W. Marcy

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S321-S325

Technical Note / dx.doi.org/10.1080/00295450.2021.1932176

Fermi at Trinity

J. I. Katz

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S326-S334

Technical Note / dx.doi.org/10.1080/00295450.2021.1927627

On the Symmetry of Blast Waves

Roy S. Baty, Scott D. Ramsey

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S335-S351

Technical Paper / dx.doi.org/10.1080/00295450.2021.1922263

Comparison Between Historic Nuclear Explosion Yield Formulas

J. P. Lestone, M. D. Rosen, P. Adsley

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S352-S355

Technical Note / dx.doi.org/10.1080/00295450.2021.1909372

Who Invented the Trinity Nuclear Test’s Christy Gadget? Patents and Evidence from the Archives

Thomas A. Chadwick, M. B. Chadwick

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S356-S373

Critical Review / dx.doi.org/10.1080/00295450.2021.1903300

Rudolf Peierls’s “Outline of the Development of the British Tube Alloy Project”: A 1945 Account of the Earliest UK Work on Atomic Energy

Richard Moore

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S374-S379

Critical Review / dx.doi.org/10.1080/00295450.2021.1910004

Estimated Radiation Doses and Projected Cancer Risks for New Mexico Residents from Exposure to Radioactive Fallout from the Trinity Nuclear Test

Steven L. Simon, André Bouville, Harold L. Beck

Nuclear Technology / Volume 207 / Number 1S / December 2021 / Pages S380-S396

Technical Note / dx.doi.org/10.1080/00295450.2021.1918985

Transition Core Analysis for HEU to LEU Fuel Conversion at the University of Missouri Research Reactor

Wilson Cowherd, John Stillman, John Gahl, Leslie Foyto, Erik Wilson

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 167-181

Technical Paper / dx.doi.org/10.1080/00295450.2020.1763720

Demand-Driven Deployment Capabilities in Cyclus, a Fuel Cycle Simulator

Gwendolyn J. Chee, Roberto E. Fairhurst Agosta, Jin Whan Bae, Robert R. Flanagan, Anthony M. Scopatz, Kathryn D. Huff

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 182-203

Technical Paper / dx.doi.org/10.1080/00295450.2020.1753444

Issues of Safety Assessment of New Russian NPP Projects in View of Current Requirements for the Probability of a Large Release

V. B. Morozov, A. E. Kiselev, A. A. Kiselev, K. S. Dolganov, D. Yu. Tomashchik, S. N. Krasnoperov

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 204-216

Technical Paper / dx.doi.org/10.1080/00295450.2020.1767998

Tellurium Behavior in the Containment Sump: Dissolution, Redox, and Radiolysis Effects

Anna-Elina Pasi, Henrik Glänneskog, Mark R. St.-J Foreman, Christian Ekberg

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 217-227

Technical Paper / dx.doi.org/10.1080/00295450.2020.1762456

Development of a Lumped Parameter Dynamic Degassing Model for Spray-Heating Degasser and Its Application in the Pressurizer of a Pressurized Water Reactor

Xianping Zhong, Jiyang Yu, Xiaolong Zhang, Muhammad Saeed, Yi Li, Zhihui Chen, Bin Tang, Yan Sun, Tao Huang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 228-246

Technical Paper / dx.doi.org/10.1080/00295450.2020.1763097

Semianalytical Solution to Near-Field Temperature in Nuclear Waste Repository

Xiangyun Zhou, Annan Zhou, De’An Sun, Daichao Sheng

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 247-262

Technical Paper / dx.doi.org/10.1080/00295450.2020.1756161

Recovery of Zirconium from Zircaloys Using a Hydrochlorination Process

Rosendo Borjas Nevarez, Bruce McNamara, Frederic Poineau

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 263-269

Technical Paper / dx.doi.org/10.1080/00295450.2020.1757961

The PyNE-Based Burnup Analysis Method for Accelerator-Driven Subcritical Systems

Jin-Yang Li, Long Gu, Hu-Shan Xu, Yong Dai, You-Peng Zhang, Cun-Feng Yao, Rui Yu, Lu Zhang, Sheng Yang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 270-284

Technical Paper / dx.doi.org/10.1080/00295450.2020.1757963

An Optimized Method for Bonner Sphere Spectrometer Design and Validation by Measuring ²⁵²Cf Spectra

Qingjun Zhu, Xianfang Meng, Wuhui Chen, Songlin Liu, Kai Huang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 285-291

Technical Paper / dx.doi.org/10.1080/00295450.2020.1750250

Optimized Digital Sallen-Key Shaping Algorithm for Radiation Detector Signal Processing

Song Wengang, Zhang Lijun, Wang Guanying, Li Qiang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 292-298

Technical Paper / dx.doi.org/10.1080/00295450.2020.1747838

Design and Optimization Based on Monte Carlo Method of a Range Shifter for Proton Therapy

Yecheng Yu, Ping Tan, Yinjie Lin, Yuying Hu, Huidong Guo, Hao Lei, Zhongqi Zhang, Jiadong Li, Delin Hu

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 299-315

Technical Paper / dx.doi.org/10.1080/00295450.2020.1747839

The Inventory and Source Term Simulation of the Argonaut Nuclear Reactor Inside a Severe Accident

Anderson M. S. Alves, Adino Heimlich, Fernando Lamego, Celso M. F. Lapa

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 316-322

Technical Note / dx.doi.org/10.1080/00295450.2020.1747840

Modeling Hydrogen Explosion in Level 1 PSA

Julien Beaucourt, Gabriel Georgescu

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 323-334

Technical Paper / dx.doi.org/10.1080/00295450.2020.1770530

Operator Action–Induced Two-Phase Flow Condition Resulting in Performance Degradation of Interfacing Passive System

Douglas A. Fynan, Jinhee Park

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 335-351

Technical Paper / dx.doi.org/10.1080/00295450.2020.1760704

Extension of a Level 2 PSA Event Tree Based on Results of a Probabilistic Dynamic Safety Analysis of Induced Steam Generator Tube Rupture

Sören Johst, Michael Hage, Jörg Peschke

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 352-362

Technical Paper / dx.doi.org/10.1080/00295450.2020.1766347

Mutual Integration of Classical and Dynamic PRA

Diego Mandelli, Andrea Alfonsi, Congjian Wang, Zhegang Ma, Carlo Parisi, Tunc Aldemir, Curtis Smith, Robert Youngblood

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 363-375

Technical Paper / dx.doi.org/10.1080/00295450.2020.1776030

Dynamic PRA-Based Estimation of PWR Coping Time Using a Surrogate Model for Accident Tolerant Fuel

Robby Christian, Asad Ullah Amin Shah, Hyun Gook Kang

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 376-388

Technical Paper / dx.doi.org/10.1080/00295450.2020.1777035

Dynamic PRA Methods to Evaluate the Impact on Accident Progression of Accident Tolerant Fuels

Diego Mandelli, Carlo Parisi, Nolan Anderson, Zhegang Ma, Hongbin Zhang

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 389-405

Technical Paper / dx.doi.org/10.1080/00295450.2020.1794234

Reevaluating the Current U.S. Nuclear Regulatory Commission’s Safety Goals

Vinod Mubayi, Robert Youngblood

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 406-412

Technical Paper / dx.doi.org/10.1080/00295450.2020.1775452

Technical Evaluation of the Margins Between Established Risk Goals and Health Objectives for Nuclear Power Plants

Fernando Ferrante, Stuart Lewis

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 413-423

Technical Paper / dx.doi.org/10.1080/00295450.2020.1775451

Understanding and Effectively Managing Conservatisms in Safety Analysis of Nonreactor Nuclear Facilities

Mohammad Modarres, Steven Krahn, James O’Brien

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 424-440

Technical Paper / dx.doi.org/10.1080/00295450.2020.1805258

State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios

S. Tina Ghosh, Hossein Esmaili, Alfred Hathaway, Nathan Bixler, Dusty Brooks, Matthew Dennis, Douglas Osborn, Kyle Ross, Kenneth Wagner

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 441-451

Technical Paper / dx.doi.org/10.1080/00295450.2021.1875737

Use of Risk Insights in the Practical Implementation of an Integrated Risk-Informed Decision-Making Framework

Fernando Ferrante, Stuart Lewis, Gareth Parry, Donald Dube, James Chapman

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 452-459

Technical Note / dx.doi.org/10.1080/00295450.2020.1782693

A Novel Approach to Realistic Conservatism in Nuclear Criticality Safety Analysis

Robert B. Hayes

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 460-467

Technical Note / dx.doi.org/10.1080/00295450.2020.1762472

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

Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT

Nicolas Woolstenhulme, Colby Jensen, Charles Folsom, Robert Armstrong, Junsoo Yoo, Daniel Wachs

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 637-652

Technical Paper / dx.doi.org/10.1080/00295450.2020.1807280

TRACE Analysis of a Loss of Alternating-Current Power Without Rod Insertion for the NuScale Power Module—I: Basic Event Progression and Long-Term Behavior

Peter Yarsky

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 653-664

Technical Paper / dx.doi.org/10.1080/00295450.2020.1800308

TRACE Analysis of a Loss of Alternating-Current Power Without Rod Insertion for the NuScale Power Module—II: Sensitivity to Varying Initial Temperature

Peter Yarsky

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 665-679

Technical Paper / dx.doi.org/10.1080/00295450.2020.1810465

Integral Effect Test and MARS-KS Calculation with Uncertainty Propagation Analysis for Direct Vessel Injection Line Break Intermediate-Break Loss-of-Coolant Accident

Byoung-Uhn Bae, Jae-Bong Lee, Yu-Sun Park, Jong-Rok Kim, Seok Cho, Kyoung-Ho Kang

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 680-691

Technical Paper / dx.doi.org/10.1080/00295450.2020.1796078

Enhancing the One-Dimensional SFR Thermal Stratification Model via Advanced Inverse Uncertainty Quantification Methods

Cihang Lu, Zeyun Wu, Xu Wu

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 692-710

Technical Paper / dx.doi.org/10.1080/00295450.2020.1805259

A Radiation-Tolerant Wireless Communication System for Severe Accident Monitoring Without Relying on Rad-Hardened Electronic Components

Qiang Huang, Jin Jiang

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 711-725

Technical Paper / dx.doi.org/10.1080/00295450.2020.1794436

Sampling and Analysis of PWR Primary Cooling System Corrosion Products Using an EPMA

Yang Hong Jung, Boung Ok Yoo

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 726-734

Technical Paper / dx.doi.org/10.1080/00295450.2020.1805250

Application of Flaw Updating Process on Probabilistic Integrity Analysis for a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks

Hsoung-Wei Chou, Pin-Chiun Huang, Yuh-Ming Ferng

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 735-749

Technical Paper / dx.doi.org/10.1080/00295450.2020.1796091

A Versatile Remediation Module for Remote Repair of Spent Nuclear Fuel and High-Level Waste Storage Containers

Stylianos Chatzidakis, Dominic Giuliano, Jeremy Slade, Wei Tang, Roger Miller, Steve Reeves, John Scaglione, Robert Howard

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 750-760

Technical Paper / dx.doi.org/10.1080/00295450.2020.1800309

Simulation of the Fast Reactor Fuel Assembly Duct-Bowing Reactivity Effect Using Monte Carlo Neutron Transport and Finite Element Analysis

Edward Lum, Chad L. Pope

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 761-770

Technical Paper / dx.doi.org/10.1080/00295450.2020.1794190

A Concept Study on Advanced Radioisotope Solid Solutions and Mixed-Oxide Fuel Forms for Future Space Nuclear Power Systems

Richard M. Ambrosi, Daniel P. Kramer, Emily Jane Watkinson, Ramy Mesalam, Alessandra Barco

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 773-781

Technical Paper / dx.doi.org/10.1080/00295450.2021.1888616

Empirical Analysis of the Multi-Mission Radioisotope Thermoelectric Generator Qualification Unit Operated at a Low Thermal Inventory with Potential for Improved End-of-Life Power

Christofer E. Whiting

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 782-789

Technical Paper / dx.doi.org/10.1080/00295450.2020.1831874

Development of Engineering Qualification Model of a Small ETG for a Launch Environmental Test

Jintae Hong, Kwang-Jae Son, Jong-Bum Kim, Jin-Joo Kim

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 790-800

Technical Paper / dx.doi.org/10.1080/00295450.2020.1832417

Development of a Novel Miniature Power Converter for Low-Power Radioisotope Heat Sources: Numerical and Experimental Results

Francisco I. Valentín, Gregory Daines

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 801-814

Technical Paper / dx.doi.org/10.1080/00295450.2020.1826271

Fabrication of UN-Mo CERMET Nuclear Fuel Using Advanced Manufacturing Techniques

Alicia M. Raftery, Rachel L. Seibert, Daniel R. Brown, Michael P. Trammell, Andrew T. Nelson, Kurt A. Terrani

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 815-824

Technical Paper / dx.doi.org/10.1080/00295450.2020.1823187

Toward an In-Depth Material Model for Cermet Nuclear Thermal Rocket Fuel Elements

William C. Tucker, Piyas Chowdhury, Lauren J. Abbott, Justin B. Haskins

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 825-835

Technical Paper / dx.doi.org/10.1080/00295450.2020.1850162

Trade-Offs Between Space Nuclear Systems Fueled with Highly Enriched Uranium and Low-Enriched Uranium

Bhavya Lal, Jericho Locke

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 836-843

Technical Paper / dx.doi.org/10.1080/00295450.2020.1847565

Considerations for Implementing Presidential Memorandum-20 Guidelines for Nuclear Safety Launch Authorization for Future Civil Space Missions

Yale Chang

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 844-850

Technical Note / dx.doi.org/10.1080/00295450.2020.1855946

Operational Considerations for Space Fission Power and Propulsion Platforms

Andrew C. Klein, Allen Camp, Patrick McClure, Susan Voss, Elan Borenstein, Paul VanDamme

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 851-859

Technical Note / dx.doi.org/10.1080/00295450.2020.1843350

Stay Cool—Alternatives for Long-Term Storage of Large Quantities of Liquid Hydrogen on a Mars Transfer Vehicle

Nicholas A. Morris, L. Dale Thomas, D. Keith Hollingsworth

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 860-865

Technical Note / dx.doi.org/10.1080/00295450.2020.1819157

Novel Deep Space Nuclear Electric Propulsion Spacecraft

Troy Howe, Steve Howe, Jack Miller

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 866-875

Technical Note / dx.doi.org/10.1080/00295450.2020.1832814

Space Nuclear Power and Propulsion at USNC-Tech

Paolo Venneri, Michael Eades

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 876-881

Technical Summary / dx.doi.org/10.1080/00295450.2021.1895662

Space Nuclear Propulsion Fuel and Moderator Development Plan Conceptual Testing Reference Design

Jeremy L. Gustafson

Nuclear Technology / Volume 207 / Number 6 / June 2021 / Pages 882-884

Technical Summary / dx.doi.org/10.1080/00295450.2021.1890991

Scalable Feature Tracking for Finite Element Meshes Demonstrated with a Novel Phase-Field Grain Subdivision Model

Cody J. Permann, Andrea M. Jokisaari, Michael R. Tonks, Daniel Schwen, Derek R. Gaston, Fande Kong, Robert Hiromoto, Richard C. Martineau

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 885-904

Technical Paper / dx.doi.org/10.1080/00295450.2020.1843893

Automatic Differentiation in MetaPhysicL and Its Applications in MOOSE

Alexander Lindsay, Roy Stogner, Derek Gaston, Daniel Schwen, Christopher Matthews, Wen Jiang, Larry K. Aagesen, Robert Carlsen, Fande Kong, Andrew Slaughter, Cody Permann, Richard Martineau

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 905-922

Technical Paper / dx.doi.org/10.1080/00295450.2020.1838877

Continuous Integration, In-Code Documentation, and Automation for Nuclear Quality Assurance Conformance

Andrew E. Slaughter, Cody J. Permann, Jason M. Miller, Brian K. Alger, Stephen R. Novascone

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 923-930

Technical Paper / dx.doi.org/10.1080/00295450.2020.1826804

Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh

Derek R. Gaston, Benoit Forget, Kord S. Smith, Logan H. Harbour, Gavin K. Ridley, Guillaume G. Giudicelli

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 931-953

Technical Paper / dx.doi.org/10.1080/00295450.2021.1871995

BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms

Richard L. Williamson, Jason D. Hales, Stephen R. Novascone, Giovanni Pastore, Kyle A. Gamble, Benjamin W. Spencer, Wen Jiang, Stephanie A. Pitts, Albert Casagranda, Daniel Schwen, Adam X. Zabriskie, Aysenur Toptan, Russell Gardner, Christoper Matthews, Wenfeng Liu, Hailong Chen

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 954-980

Technical Paper / dx.doi.org/10.1080/00295450.2020.1836940

Grizzly and BlackBear: Structural Component Aging Simulation Codes

Benjamin W. Spencer, William M. Hoffman, Sudipta Biswas, Wen Jiang, Alain Giorla, Marie A. Backman

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 981-1003

Technical Paper / dx.doi.org/10.1080/00295450.2020.1868278

Multiscale Simulations of Thermal Transport in W-UO₂ CERMET Fuel for Nuclear Thermal Propulsion

Marina Sessim, Michael R. Tonks

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 1004-1014

Technical Paper / dx.doi.org/10.1080/00295450.2021.1910005

Pronghorn: A Multidimensional Coarse-Mesh Application for Advanced Reactor Thermal Hydraulics

A. J. Novak, R. W. Carlsen, S. Schunert, P. Balestra, D. Reger, R. N. Slaybaugh, R. C. Martineau

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 1015-1046

Technical Paper / dx.doi.org/10.1080/00295450.2020.1825307

Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application

Yaqi Wang, Sebastian Schunert, Javier Ortensi, Vincent Laboure, Mark DeHart, Zachary Prince, Fande Kong, Jackson Harter, Paolo Balestra, Frederick Gleicher

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 1047-1072

Technical Paper / dx.doi.org/10.1080/00295450.2020.1843348

MASTODON: An Open-Source Software for Seismic Analysis and Risk Assessment of Critical Infrastructure

Swetha Veeraraghavan, Chandrakanth Bolisetti, Andrew Slaughter, Justin Coleman, Somayajulu Dhulipala, William Hoffman, Kyungtae Kim, Efe Kurt, Robert Spears, Lynn Munday

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 1073-1095

Technical Paper / dx.doi.org/10.1080/00295450.2020.1807282

Sockeye: A One-Dimensional, Two-Phase, Compressible Flow Heat Pipe Application

Joshua E. Hansel, Ray A. Berry, David Andrs, Matthias S. Kunick, Richard C. Martineau

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 1096-1117

Technical Paper / dx.doi.org/10.1080/00295450.2020.1861879

Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors

Elia Merzari, Haomin Yuan, Misun Min, Dillon Shaver, Ronald Rahaman, Patrick Shriwise, Paul Romano, Alberto Talamo, Yu-Hsiang Lan, Derek Gaston, Richard Martineau, Paul Fischer, Yassin Hassan

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 1118-1141

Technical Paper / dx.doi.org/10.1080/00295450.2020.1824471

Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf

Christopher Matthews, Vincent Laboure, Mark DeHart, Joshua Hansel, David Andrs, Yaqi Wang, Javier Ortensi, Richard C. Martineau

Nuclear Technology / Volume 207 / Number 7 / July 2021 / Pages 1142-1162

Technical Paper / dx.doi.org/10.1080/00295450.2021.1906474

Covert Cognizance: A Novel Predictive Modeling Paradigm

Arvind Sundaram, Hany Abdel-Khalik

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1163-1181

Technical Paper / dx.doi.org/10.1080/00295450.2020.1812349

Reactor Physics Analysis Assessment of Feasibility of Using Advanced, Nonconventional Fuels in a Pressure Tube Heavy Water Reactor to Destroy Long-Lived Fission Products

B. P. Bromley, A. V. Colton

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1182-1192

Technical Paper / dx.doi.org/10.1080/00295450.2020.1812318

Reactor Physics Assessment of Potential Feasibility of Using Advanced, Nonconventional Fuels in a Pressure Tube Heavy Water Reactor to Destroy Americium and Curium

B. P. Bromley, A. V. Colton

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1193-1215

Technical Paper / dx.doi.org/10.1080/00295450.2020.1853466

Steady-State Subchannel Thermal-Hydraulic Assessment of Advanced Uranium-Based and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors

A. Nava-Dominguez, S. Liu, T. Beuthe, B. P. Bromley, A. V. Colton

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1216-1236

Technical Paper / dx.doi.org/10.1080/00295450.2020.1813463

Water Migration and Swelling in Engineered Barrier Materials for Radioactive Waste Disposal

Joanna McFarlane, Lawrence M. Anovitz, Michael C. Cheshire, Victoria H. DiStefano, Hassina Z. Bilheux, Jean-Christophe Bilheux, Luke L. Daemen, Richard E. Hale, Robert L. Howard, A. Ramirez-Cuesta, Louis J. Santodonato, Markus Bleuel, Daniel S. Hussey, David L. Jacobson, Jacob M. LaManna, Edmund Perfect, Logan M. Qualls

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1237-1256

Technical Paper / dx.doi.org/10.1080/00295450.2020.1812348

Emissivity of Grade 91 Ferritic Steel: Additional Measurements on Role of Surface Conditions and Oxidation

Faten N. Al Zubaidi, Kyle L. Walton, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1257-1269

Technical Paper / dx.doi.org/10.1080/00295450.2020.1808394

Development of a Gamma-Ray Radionuclide Library for the Identification of Gamma Spectra

Pola Lydia Lagari, Styliani Pantopoulou, Miltos Alamaniotis, Lefteri H. Tsoukalas

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1270-1279

Technical Paper / dx.doi.org/10.1080/00295450.2020.1816743

Development of an Integrated Computer Code System for Analyzing Irradiation Behaviors of a Fast Reactor Fuel

Tomoyuki Uwaba, Junichi Nemoto, Masahiro Ito, Ikuo Ishitani, Norihiro Doda, Masaaki Tanaka, Satoshi Ohtsuka

Nuclear Technology / Volume 207 / Number 8 / August 2021 / Pages 1280-1289

Technical Note / dx.doi.org/10.1080/00295450.2020.1810977

ASTRID, Back to the Future: Bridging Scales in the Development of Nuclear Infrastructures

Stéphanie Tillement, Frédéric Garcias

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1291-1311

Technical Paper / dx.doi.org/10.1080/00295450.2020.1868892

From “Inherently Safe” to “Proliferation Resistant”: New Perspectives on Reactor Designs

Sonja D. Schmid

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1312-1328

Technical Paper / dx.doi.org/10.1080/00295450.2020.1837584

NEA Framing Nuclear Megaproject “Pathologies”: Vices of the Modern Western Society?

Markku Lehtonen

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1329-1350

Technical Paper / dx.doi.org/10.1080/00295450.2021.1885952

Breaking Out of a Niche: Lessons for SMRs from Sustainability Transitions Studies

Mariia Iakovleva, Jeremy Rayner, Ken Coates

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1351-1365

Technical Paper / dx.doi.org/10.1080/00295450.2020.1855947

Styles of Revaluation: The Case of the Levelized Cost of Electricity

Başak Saraç-Lesavre

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1366-1376

Technical Paper / dx.doi.org/10.1080/00295450.2021.1884492

Mankala Chronicles: Nuclear Energy Financing and Cooperative Corporate Form in Finland

Vincent Ialenti

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1377-1393

Technical Paper / dx.doi.org/10.1080/00295450.2020.1868890

Social Scientists in an Adversarial Environment: The Nuclear Regulatory Commission and Organizational Factors Research

Thomas R. Wellock

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1394-1409

Technical Paper / dx.doi.org/10.1080/00295450.2020.1826273

Revisiting Safety Culture: The Benefits of a New Cultural Analysis Framework for Safety Management

Elsa Gisquet, Sophie Beauquier, Emilie Poulain

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1410-1422

Technical Paper / dx.doi.org/10.1080/00295450.2020.1868891

Structural Ignorance of Expertise in Nuclear Safety Controversies: Case Analysis of Post-Fukushima Japan

Kohta Juraku, Shin-Etsu Sugawara

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1423-1441

Technical Paper / dx.doi.org/10.1080/00295450.2021.1908075

“Economizing” TEPCO’s Responsibility for the Fukushima Daiichi Nuclear Power Plant Accident

Eri Kanamori

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1442-1455

Technical Paper / dx.doi.org/10.1080/00295450.2020.1865028

Changing the System Culture: Mobilizing the Social Sciences in the Swedish Nuclear Waste System

Thomas Kaiserfeld, Arne Kaijser

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1456-1468

Technical Paper / dx.doi.org/10.1080/00295450.2020.1832815

The Power and Limits of Classification: Radioactive Waste Categories as Reshaped by Disposal Options

Céline Parotte

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1469-1482

Technical Paper / dx.doi.org/10.1080/00295450.2021.1888618

Geographies of Energy—A Course in Sociotechnical Decision Making

Lisa Marshall

Nuclear Technology / Volume 207 / Number 9 / September 2021 / Pages 1483-1490

Technical Paper / dx.doi.org/10.1080/00295450.2021.1895408

Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm

G. L. Beausoleil, C. Petrie, W. Williams, A. Jokisaari, L. Capriotti, S. Novascone, C. Adkins, M. Kerr

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1491-1510

Critical Review / dx.doi.org/10.1080/00295450.2020.1826272

Sensitivity Studies to Assess the Impact of Geometry and Operating/Boundary Condition Perturbations on Thermal-Hydraulic Behavior of Advanced Fuel Channels in Pressure Tube Heavy Water Reactors with Uranium and Thorium-Based Fuels

B. P. Bromley, Z. Cheng, A. Nava Dominguez, A. V. Colton

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1511-1537

Technical Paper / dx.doi.org/10.1080/00295450.2020.1827658

Startup Test Plan and Predictions for Highly Enriched Uranium to Low-Enriched Uranium Fuel Conversion at the University of Missouri Research Reactor

Wilson Cowherd, John Stillman, Leslie Foyto, Erik Wilson, Kiratadas Kutikkad, Nickie Peters, John Gahl

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1538-1563

Technical Paper / dx.doi.org/10.1080/00295450.2020.1829427

Multi-Index Measurement of Fatigue Degree Under the Simulated Monitoring Task of a Nuclear Power Plant

Gang Zhang, Shibo Mei, Kaijie Xie, Zhen Yang

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1564-1577

Technical Paper / dx.doi.org/10.1080/00295450.2020.1824965

Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors

Kieran Dolan, Steven Huang, Micah Hackett, Lin-Wen Hu

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1578-1598

Technical Paper / dx.doi.org/10.1080/00295450.2020.1829428

Coupled Computational Fluid Dynamics–Discrete Element Method Study of Bypass Flows in a Pebble Bed Reactor

Mauricio E. Tano, Jean C. Ragusa

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1599-1614

Technical Paper / dx.doi.org/10.1080/00295450.2020.1820830

Comparison of Triggered Steam Explosion Behavior According to Corium Injection Mode in TROI Facility from TEXAS-V Code Simulations

Sang Ho Kim, Seong-Wan Hong, Rae-Joon Park

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1615-1632

Technical Paper / dx.doi.org/10.1080/00295450.2020.1820827

On the Amount of Moderation in the CANDU Lattice

Benjamin Rouben, Eleodor Nichita

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1633-1638

Technical Note / dx.doi.org/10.1080/00295450.2020.1827884

Effect of Soil Properties and Input Motion on Site Amplification Using Validated Nonlinear Soil Model

Samyog Shrestha, Efe G. Kurt, Kyungtae Kim, Arun Prakash, Ayhan Irfanoglu

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1639-1663

Technical Paper – Special section on the Seismic Analysis and Risk Assessment of Nuclear Facilities / dx.doi.org/10.1080/00295450.2021.1920798

Seismic Performance of Deeply Embedded Conceptual Advanced Reactors: Three-Dimensional Nonlinear Soil-Structure Interaction Analyses

Efe G. Kurt, Robert Spears

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1664-1686

Technical Paper – Special section on the Seismic Analysis and Risk Assessment of Nuclear Facilities / dx.doi.org/10.1080/00295450.2020.1843952

Cost- and Risk-Based Seismic Design Optimization of Nuclear Power Plant Safety Systems

Chandrakanth Bolisetti, Justin Coleman, William Hoffman, Andrew Whittaker

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1687-1711

Technical Paper – Special section on the Seismic Analysis and Risk Assessment of Nuclear Facilities / dx.doi.org/10.1080/00295450.2021.1932175

Seismic Risk Assessment of Safety-Critical Nuclear Facilities for the Purpose of Risk-Informed Periodic Reevaluation

Somayajulu L. N. Dhulipala, Chandrakanth Bolisetti, Richard Yorg, Philip Hashimoto, Justin L. Coleman, Mark Cox

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1712-1724

Technical Note – Special section on the Seismic Analysis and Risk Assessment of Nuclear Facilities / dx.doi.org/10.1080/00295450.2020.1792743

Evaluating the Improvement of Cross-Correlation–Based Flow Measurement by Periodic Fluid Injection

Xiong Gao, Jamie B. Coble, A. C. Hines, Belle R. Upadhyaya, J. Wesley Hines

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1725-1745

Regular Technical Paper / dx.doi.org/10.1080/00295450.2020.1831873

Enhancements to the New TREAT Automatic Reactor Control System (ARCS)

Benjamin Allen Baker, Kurt D. Fielding, Jacob E. Hansen, Tanner Ellsworth

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1746-1752

Regular Technical Paper / dx.doi.org/10.1080/00295450.2020.1833621

Electroencephalography-Based Intention Monitoring to Support Nuclear Operators’ Communications for Safety-Relevant Tasks

Jung Hwan Kim, Chul Min Kim, Yong Hee Lee, Man-Sung Yim

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1753-1767

Regular Technical Paper / dx.doi.org/10.1080/00295450.2020.1837583

Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3

Georgeta Radulescu, Kaushik Banerjee, Thomas M. Miller, Douglas E. Peplow

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1768-1783

Regular Technical Paper / dx.doi.org/10.1080/00295450.2020.1842702

Passive Reactivity Control Device with Thermal Expansion of Liquid In-Gd Alloy

Rei Kimura, Shohei Kanamura, Yuya Takahashi, Kazuhito Asano

Nuclear Technology / Volume 207 / Number 11 / November 2021 / Pages 1784-1792

Regular Technical Paper / dx.doi.org/10.1080/00295450.2020.1843953

Transitioning to a Sustainable Thorium Fuel Cycle in Pressurized Water Reactors Using Bimetallic Thorium-Zirconium Alloy Cladding

Swaminathan Vaidyanathan

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1793-1809

Technical Paper / dx.doi.org/10.1080/00295450.2020.1846987

Evaluation of Fixed Absorber Reactivity Measurement in the Prototype Fast Reactor Monju

Kazuya Ohgama, Hiroki Katagiri, Atsushi Takegoshi, Taira Hazama

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1810-1820

Technical Paper / dx.doi.org/10.1080/00295450.2020.1846481

Feasibility Assessment of a Natural-Circulation Salt Irradiation Loop in the Advanced Test Reactor

Abdalla Abou-Jaoude, Samuel A. Walker, Sandesh Bhaskar, Wei Ji

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1821-1841

Technical Paper / dx.doi.org/10.1080/00295450.2020.1843954

Investigation of the CRUD Layer in Failed PWR Fuel Using an EPMA

Yang Hong Jung, Hee Moon Kim

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1842-1850

Technical Paper / dx.doi.org/10.1080/00295450.2020.1845057

Coupling Gothic and RELAP5 for Passive Containment Cooling Modeling

J. C. Kang, J. S. Jeong, D. H. Lee, T. L. George, J. W. Lane, S. G. Thomasson

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1851-1864

Technical Paper / dx.doi.org/10.1080/00295450.2020.1858628

Parametric Analysis of an Optical Fiber–Based Gamma Thermometer for University Research Reactors Using an Analytic Thermal Model

Anthony Birri, Christian M. Petrie, Thomas E. Blue

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1865-1872

Technical Paper / dx.doi.org/10.1080/00295450.2020.1844532

Short-Term Assessment of Radiological Impact and Potential Risk to Workers and Public from Argonaut Nuclear Reactor Accidental Release

Paula C. Souza, André S. Aguiar, Adino Heimlich, Celso M. F. Lapa, Fernando Lamego

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1873-1888

Technical Paper / dx.doi.org/10.1080/00295450.2020.1846986

Application of Cable Condition Monitoring Technologies to Assess Age-Related Degradation of Industrial Cables Installed in Harsh Environments

Trevor Toll, Patrick Ward, Codi Ferree, Casey Sexton, Gary Harmon

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1889-1901

Technical Paper / dx.doi.org/10.1080/00295450.2020.1855289

Assessment of the Maximum Temperature of Simplified High Heat Radioactive Glass in Interim Storage and Deep Geological Disposal

Minsuk Seo

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1902-1912

Technical Paper / dx.doi.org/10.1080/00295450.2020.1860614

Assessment of Terrorist Attack Risk of a BWR Nuclear Power Plant Using Monte Carlo Simulations

Yi-Cheng Tian, Min Lee

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1913-1933

Technical Note / dx.doi.org/10.1080/00295450.2020.1843955