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Volume 206

Number 1 | Number 1S | Number 2 | Number 3 | Number 4 | Number 5 | Number 6 | Number 7 | Number 8 | Number 9 | Number 10 | Number 11 | Number 12

Number 1

A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties

Dawn E. Janney, Steven L. Hayes, Cynthia A. Adkins

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 1-22

Critical Review / dx.doi.org/10.1080/00295450.2019.1623617

Pyrolytic Carbon Coating Effects on Oxide and Carbide Kernels Intended for Nuclear Fuel Applications

Miles F. Beaux, II, Douglas R. Vodnik, Reuben J. Peterson, Bryan L. Bennett, Kevin M. Hubbard, Brian M. Patterson, Jeffrey D. Goettee, James D. Jurney, Graham M. King, Alice I. Smith, Eric L. Tegtmeier, Erik P. Luther, Venkateswara R. Dasari, (DV Rao), David J. Devlin, Igor O. Usov

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 23-31

Technical Paper / dx.doi.org/10.1080/00295450.2019.1618683

Displacement Cascades in Monocrystalline Silicon: Effects of Temperature, Strain, and PKA Energy

Yuan Zhou, Bing Chen, Hongyu He, Bo Li, Xinlin Wang

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 32-39

Technical Paper / dx.doi.org/10.1080/00295450.2019.1613850

Rapid Clogging of High-Efficiency Particulate Air Filters During In-Cell Solvent Fires at Reprocessing Facilities

Takuya Ohno, Shinsuke Tashiro, Yuki Amano, Ryoichiro Yoshida, Hitoshi Abe

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 40-47

Technical Paper / dx.doi.org/10.1080/00295450.2019.1620057

Fuel Cycle Analysis of Novel Assembly Design for Thorium-Uranium-Ceramic–Fueled Thermal, High-Conversion Reactor

N. Kaffezakis, D. Kotlyar

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 48-72

Technical Paper / dx.doi.org/10.1080/00295450.2019.1616475

A Method to Estimate Fission Product Concentration Uncertainty in a Multi-Time-Step MCNP6 Code Nuclear Fuel Burnup Calculation

Yasuhiro Minamigawa, Evans D. Kitcher, Sunil S. Chirayath

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 73-81

Technical Paper / dx.doi.org/10.1080/00295450.2019.1624429

Effectiveness of Model-Based Defenses for Digitally Controlled Industrial Systems: Nuclear Reactor Case Study

Yeni Li, Elisa Bertino, Hany S. Abdel-Khalik

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 82-93

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626170

Using Artificial Neural Networks for Predicting Mental Workload in Nuclear Power Plants Based on Eye Tracking

Yiqian Wu, Zhiyao Liu, Ming Jia, Cong Chi Tran, Shengyuan Yan

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 94-106

Technical Paper / dx.doi.org/10.1080/00295450.2019.1620055

Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems

Douglas E. Peplow, Kaushik Banerjee, Gregory G. Davidson, Ian R. Stewart, Mathew W. Swinney, Jackson N. Wagner

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 107-125

Technical Paper / dx.doi.org/10.1080/00295450.2019.1625663

Investigative Study of Neutronic Safety Parameters of HPR and EPR Using the MCNP Code

R G. Abrefah, P. M. Atsu, R. B. M. Sogbadji

Nuclear Technology / Volume 206 / Number 1 / January 2020 / Pages 126-132

Technical Note / dx.doi.org/10.1080/00295450.2019.1618130

Number 1S

Kilopower Project: The KRUSTY Fission Power Experiment and Potential Missions

Patrick R. McClure, David I. Poston, Marc A. Gibson, Lee S. Mason, R. Chris Robinson

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 1-12

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2020.1722554

KRUSTY Reactor Design

David I. Poston, Marc A. Gibson, Thomas Godfroy, Patrick R. McClure

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 13-30

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2020.1725382

Heat Transport and Power Conversion of the Kilopower Reactor Test

Marc A. Gibson, David I. Poston, Patrick R. McClure, James L. Sanzi, Thomas J. Godfroy, Maxwell H. Briggs, Scott D. Wilson, Nicholas A. Schifer, Max F. Chaiken, Nissim Lugasy

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 31-42

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2019.1709364

KRUSTY Experiment: Reactivity Insertion Accident Analysis

Patrick R. McClure, David I. Poston, Steven D. Clement, Louis Restrepo, Robert Miller, Manny Negrete

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 43-55

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2020.1722544

Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component-Critical Experiments

Rene Sanchez, Travis Grove, David Hayes, Joetta Goda, George McKenzie, Jesson Hutchinson, Theresa Cutler, John Bounds, Jessie Walker, William Myers, Kristin Smith

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 56-67

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2020.1722553

Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Cold Critical Measurements

Travis Grove, David Hayes, Joetta Goda, George McKenzie, Jesson Hutchinson, Theresa Cutler, John Bounds, Jessie Walker, William Myers, Rene Sanchez

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 68-77

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2020.1712950

Results of the KRUSTY Warm Critical Experiments

David I. Poston, Marc A. Gibson, Patrick R. McClure, Rene G. Sanchez

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 78-88

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2020.1727287

Results of the KRUSTY Nuclear System Test

David I. Poston, Marc A. Gibson, Rene G. Sanchez, Patrick R. McClure

Nuclear Technology / Volume 206 / Number 1S / June 2020 / Pages 89-117

Technical Paper – Kilopower/KRUSTY special issue / dx.doi.org/10.1080/00295450.2020.1730673

Number 2

Interface-Resolved Simulations of Reactor Flows

Jun Fang, Joseph J. Cambareri, Mengnan Li, Nadish Saini, Igor A. Bolotnov

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 133-149

Critical Review / dx.doi.org/10.1080/00295450.2019.1620056

Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA

Katrien Van Tichelen, Graham Kennedy, Fabio Mirelli, Alessandro Marino, Antonio Toti, Davide Rozzia, Edoardo Cascioli, Steven Keijers, Philippe Planquart

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 150-163

Critical Review / dx.doi.org/10.1080/00295450.2019.1614803

Direct Numerical Simulation and Wall-Resolved Large Eddy Simulation in Nuclear Thermal Hydraulics

Iztok Tiselj, Cedric Flageul, Jure Oder

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 164-178

Critical Review / dx.doi.org/10.1080/00295450.2019.1614381

Thermal-Hydraulic Experimental Testing of the MYRRHA Wire-Wrapped Fuel Assembly

Graham Kennedy, Katrien Van Tichelen, Julio Pacio, Ivan Di Piazza, Heleen Uitslag-Doolaard

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 179-190

Technical Paper / dx.doi.org/10.1080/00295450.2019.1620539

Study on Reactor Vessel Air Cooling for Westinghouse Lead Fast Reactor

Jun Liao, Dan Utley

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 191-205

Technical Paper / dx.doi.org/10.1080/00295450.2019.1599614

Development of Mechanistic Source Term Analysis Tool SAS4A-FATE for Lead- and Sodium-Cooled Fast Reactors

T. Q. Hua, S. J. Lee, J. Liao, A. Moisseytsev, P. Ferroni, A. Karahan, C. Y. Paik, A. M. Tentner, T. Sofu

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 206-217

Technical Paper / dx.doi.org/10.1080/00295450.2019.1598715

On the Fluid Structure Interactions of a Wire-Wrapped Pin Bundle

C. A. Nixon, W. R. Marcum, K. M. Steer, R. B. Jackson, M. G. Martin, A. W. Weiss

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 218-230

Technical Paper / dx.doi.org/10.1080/00295450.2019.1649583

Experimental and Numerical Characterization of the Flow Field at the Core Entrance of a Water Model of a Heavy Liquid Metal–Cooled Reactor

Philippe Planquart, Chiara Spaccapaniccia, Giacomo Alessi, Sophia Buckingham, Katrien Van Tichelen

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 231-241

Technical Paper / dx.doi.org/10.1080/00295450.2019.1637240

Overview of the SAS4A Metallic Fuel Models and Extended Analysis of a Postulated Severe Accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor

A. M. Tentner, A. Karahan, S. H. Kang

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 242-254

Technical Paper / dx.doi.org/10.1080/00295450.2019.1636589

Wall-Modeled Large Eddy Simulation of the Flow Through PWR Fuel Assemblies at ReH = 66 000—Validation on CALIFS Experimental Setup

Marie-Charlotte Gauffre, Sofiane Benhamadouche, Pierre-Bernard Badel

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 255-265

Technical Paper / dx.doi.org/10.1080/00295450.2019.1642684

Direct Numerical Simulation of Turbulent Flow Inside a Differentially Heated Composite Cavity

Javier Martínez, Elia Merzari, Michael Acton, Emilio Baglietto

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 266-282

Technical Paper / dx.doi.org/10.1080/00295450.2019.1595312

High-Performance Computing for Nuclear Reactor Design and Safety Applications

Afaque Shams, Dante De Santis, Adam Padee, Piotr Wasiuk, Tobiasz Jarosiewicz, Tomasz Kwiatkowski, Sławomir Potempski

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 283-295

Technical Paper / dx.doi.org/10.1080/00295450.2019.1642683

Numerical Simulation of Isothermal Flow Across Slant Five-Tube Bundle with Spectral Element Method Code Nek5000

Mustafa Alper Yildiz, Haomin Yuan, Elia Merzari, Yassin Hassan

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 296-306

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626176

Velocity and Scalar Fields of a Turbulent Buoyant Jet in the Self-Similar Region

Sunming Qin, Benedikt Krohn, Victor Petrov, Annalisa Manera

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 307-321

Technical Paper / dx.doi.org/10.1080/00295450.2019.1591155

Thermal-Hydraulic and Neutronic Phenomena Important in Modeling and Simulation of Liquid-Fuel Molten Salt Reactors

Nicholas R. Brown, David J. Diamond, Stephen Bajorek, Richard Denning

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 322-338

Technical Paper / dx.doi.org/10.1080/00295450.2019.1590077

Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux

Soon K. Lee, Maolong Liu, Nicholas R. Brown, Kurt A. Terrani, Youho Lee

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 339-346

Technical Paper / dx.doi.org/10.1080/00295450.2019.1670010

Interfacial Structures in Bubbly-to-Slug Transition Flows in a Duct

Guanyi Wang, Qingzi Zhu, Mamoru Ishii

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 347-357

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626175

Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces

Mingfu He, Youho Lee

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 358-374

Technical Paper / dx.doi.org/10.1080/00295450.2019.1626177

Simulation of Boiling Two-Phase Flow in a Helical Coil Steam Generator Using the Spectral Element Code Nek-2P

Dillon R. Shaver, Nate Salpeter, Ananias Tomboulides, Prasad Vegendla, Adrian Tentner, W. David Pointer, Elia Merzari

Nuclear Technology / Volume 206 / Number 2 / February 2020 / Pages 375-387

Technical Paper / dx.doi.org/10.1080/00295450.2019.1664199

Number 3

Liquid Film Thickness in Vertical Circular Pipes Under Flooding Conditions at the Top End

Toshiya Takaki, Michio Murase, Koji Nishida, Raito Goda, Takeyuki Shimamura, Akio Tomiyama

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 389-400

Technical Paper / dx.doi.org/10.1080/00295450.2019.1656521

Comparison of Triggered Explosion Behavior by Corium Injection Modes in TROI Facility

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

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 401-413

Technical Paper / dx.doi.org/10.1080/00295450.2019.1654816

Uncertainty Quantification Using the MAAP5 Code of In-Vessel Hydrogen Generation in a Severe Accident at an Advanced Boiling Water Reactor

Te-Chuan Wang, Min Lee

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 414-427

Technical Paper / dx.doi.org/10.1080/00295450.2019.1653152

The CRANK System—A Simple, Robust Apparatus for Measurement of Cherenkov Light at Open-Pool Reactor

Thomas V. Holschuh, Wade R. Marcum

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 428-434

Technical Paper / dx.doi.org/10.1080/00295450.2019.1640515

Development of an In-Vessel CEDM for Small Modular Reactors

Jinseok Park, Wonho Lee, Myounggoo Lee, Yeonho Cho, Hyunmin Kim, Chulsoo Maeng

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 435-443

Technical Paper / dx.doi.org/10.1080/00295450.2019.1635363

A Revised Capsule Design for the Accelerated Testing of Advanced Reactor Fuels

G. L. Beausoleil, II, G. L. Povirk, B. J. Curnutt

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 444-457

Technical Paper / dx.doi.org/10.1080/00295450.2019.1631052

Experimental and Simulation Analysis of Hydrogen Permeation Performance of Pd/Ag Permeator Used for Tritium Processing

Yu Huang, Gaofeng Lu, Youshi Zeng, Nan Qian, Xinxin Chu, Guanghua Wang, Shengwei Wu, Wei Liu

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 458-466

Technical Paper / dx.doi.org/10.1080/00295450.2019.1633156

Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event

J. Wang, H. Yeom, P. Humrickhouse, K. Sridharan, M. Corradini

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 467-477

Technical Paper / dx.doi.org/10.1080/00295450.2019.1649566

Demonstration of the Advanced Dynamic System Modeling Tool TRANSFORM in a Molten Salt Reactor Application via a Model of the Molten Salt Demonstration Reactor

M. Scott Greenwood, Benjamin R. Betzler, A. Lou Qualls, Junsoo Yoo, Cristian Rabiti

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 478-504

Technical Paper / dx.doi.org/10.1080/00295450.2019.1627124

Conceptual Design of an Accident Prevention System for Light Water Reactors Using Artificial Neural Network and High-Speed Simulator

Li-Chi Cliff Po

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 505-513

Technical Note / dx.doi.org/10.1080/00295450.2019.1641877

Characteristics of Water Suction for a Korean Compacted Bentonite

Seok Yoon, Jun-Seo Jeon, Seeun Chang, Deuk-Hwan Lee, Seung-Rae Lee, Geon-Young Kim

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 514-525

Technical Note / dx.doi.org/10.1080/00295450.2019.1632093

Number 4

Scaling Analysis of Reactor Cavity Cooling System in HTR

Thiago D. Roberto, Celso M. F. Lapa, Antonio C. M. Alvim

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 527-543

Technical Paper / dx.doi.org/10.1080/00295450.2019.1666603

Behavior of the Density Interface of Helium Stratification by an Impinging Jet

Y. S. Na, W. Lee, S. Song

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 544-553

Technical Paper / dx.doi.org/10.1080/00295450.2019.1657328

Time Series Analysis for BWR Stability Studies

Wilmer A. Coloma, Antonella L. Costa, Claubia Pereira, Clarysson A. M. da Silva

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 554-564

Technical Paper / dx.doi.org/10.1080/00295450.2019.1662668

Surface Pressure Measurements in a Model Helical Coil Steam Generator Using Pressure Sensitive Paint

G. A. Porter, M. Delgado, Y. A. Hassan

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 565-576

Technical Paper / dx.doi.org/10.1080/00295450.2019.1666600

Development of a Li2O Sensor Based on a Yttria Stabilized Zirconia Membrane for Oxide Reduction in a Molten LiCl-Li2O Electrolyte at 650°C

G. Cao, S. Herrmann, S. Li, R. Hoover, J. King, B. Serrano-Rodriguez, K. Marsden

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 577-586

Technical Paper / dx.doi.org/10.1080/00295450.2019.1666601

Thermochemical Evaluation of Standard Electrode Potential and Gibbs Energy of Formation of PuCl3 in LiCl-KCl Eutectic Melt

Suddhasattwa Ghosh, Gurudas Pakhui, S. Suganthi, S. Nedumaran, M. Kakkum Perumal, Manish Chandra, P. Venkatesh, Bandi Prabhakara Reddy

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 587-608

Technical Paper / dx.doi.org/10.1080/00295450.2019.1666602

Genetic Algorithm Design of a Coupled Fast and Thermal Subcritical Assembly

John Pevey, Ondřej Chvála, Sarah Davis, Vladimir Sobes, J. Wes Hines

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 609-619

Technical Paper / dx.doi.org/10.1080/00295450.2019.1664198

Analysis of Depletion and Inventory of the Fuel for the MNSR Research Reactor Using the Deterministic Code DRAGON5

Jamal Al Zain, O. El Hajjaji, T. El Bardouni, M. Lahdour

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 620-636

Technical Paper / dx.doi.org/10.1080/00295450.2019.1662669

Neutronics Analysis for a High-Temperature Gas-Cooled Reactor in a Water-Flooded-Core Accident

Zhong Chen, Zi Jia Zhao, Zhongliang Lv, Yanyun Ma

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 637-650

Technical Note / dx.doi.org/10.1080/00295450.2019.1653151

Improvement of an Experimental Routine for Electrochemical Composition Measurements of SmCl3 in LiCl-KCl Eutectic Salt Systems

Hunter Andrews, Supathorn Phongikaroon

Nuclear Technology / Volume 206 / Number 4 / April 2020 / Pages 651-661

Technical Note / dx.doi.org/10.1080/00295450.2019.1670009

Number 5

Effects of Mixing Vane Spacer on Flow and Thermal Behavior of Fluid in Fuel Channels of Nuclear Reactors—A Review

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

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 663-696

Critical Review / dx.doi.org/10.1080/00295450.2019.1698257

Improved Online Localization of CANDU Fuel Defects Using Ancillary Data Sources and Neural Networks

Christopher Wallace, Curtis McEwan, Graeme West, William Aylward, Stephen McArthur

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 697-705

Technical Paper / dx.doi.org/10.1080/00295450.2019.1697174

Biaxial Creep Behavior of Nb-Modified Zircaloys

Pratik Joshi, Micah Tillman, Nilesh Kumar, Korukonda Murty, Nedim Cinbiz

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 706-716

Technical Paper / dx.doi.org/10.1080/00295450.2019.1674581

Study on Sintering Kinetics of (ThxCe1-x)O2 Ceramic Pellets Prepared via Sol-Gel Method

Berkan Çetinkaya, Hüseyin Tel, Ahmet Yaylı

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 717-727

Technical Paper / dx.doi.org/10.1080/00295450.2019.1686939

Coupled Neutronics–Thermal-Hydraulic Simulation of BEAVRS Cycle 1 Depletion by the MCS/CTF Code System

Jiankai Yu, Hyunsuk Lee, Hanjoo Kim, Peng Zhang, Deokjung Lee

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 728-742

Technical Paper / dx.doi.org/10.1080/00295450.2019.1677107

Simplified Approach for Seismic Risk Assessment of Cabinet Facility in Nuclear Power Plants Based on Cumulative Absolute Velocity

Anh-Tuan Cao, Thanh-Tuan Tran, Thi-Hong-Xuyen Nguyen, Dookie Kim

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 743-757

Technical Paper / dx.doi.org/10.1080/00295450.2019.1696643

Use of Neutron Absorbers to Influence the Neutron Transmutation Doping Process in Silicon

J. Vande Pitte, J. Wagemans, A. Gusarov, I. Uytdenhouwen, C. Detavernier, J. Lauwaert

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 758-765

Technical Paper / dx.doi.org/10.1080/00295450.2019.1697172

Penetrability of γ/n and Static Behavior of Newly Developed Concrete Using Different Passive Assay Techniques

Mohamed A. E. Abdel-Rahman, Mohamed A. E. M. Ali, Sayed A. El-Mongy

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 766-778

Technical Paper / dx.doi.org/10.1080/00295450.2019.1697173

Monte Carlo Simulation Using TOPAS for Gas Chamber Design of PBS Nozzle in Superconducting Proton Therapy Facility

Ming Wang, Jinxing Zheng, Yuntao Song, Xianhu Zeng, Ming Li, Wuquan Zhang, Pengyu Wang, Junsong Shen

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 779-790

Technical Paper / dx.doi.org/10.1080/00295450.2019.1670011

Experience in Decontamination of Naval Reactor Plants

B. A. Gusev, I. S. Orlenkov, L. N. Moskvin, N. G. Sandler, A. A. Efimov, А. M. Aleshin, V. V. Krivobokov, V. N. Vavilkin

Nuclear Technology / Volume 206 / Number 5 / May 2020 / Pages 791-803

Technical Note / dx.doi.org/10.1080/00295450.2019.1693216

Number 6

Development and Analysis of TREAT Neutronics Benchmarks

Volkan Seker, Haining Zhou, Thomas J. Downar

Nuclear Technology / Volume 206 / Number 6 / June 2020 / Pages 805-824

Technical Paper / dx.doi.org/10.1080/00295450.2019.1703464

Quasi-Diffusion Method with 3-D Cross Sections for TREAT Core Analysis

Yunlin Xu, Volkan Seker, Thomas J. Downar

Nuclear Technology / Volume 206 / Number 6 / June 2020 / Pages 825-838

Technical Paper / dx.doi.org/10.1080/00295450.2019.1672451

Enhanced Lasso Regularization-Based Self-Adaptive Feature Selection Algorithm for the High-Dimensional Uncertainty Quantification of TREAT Transient Test Modeling

Haining Zhou, Volkan Seker, Thomas Downar

Nuclear Technology / Volume 206 / Number 6 / June 2020 / Pages 839-861

Technical Paper / dx.doi.org/10.1080/00295450.2020.1746620

Multi-Resolution Analysis of a Historic Sodium Loop Experiment for TREAT

Thomas Moore, Mike Steer, Marco Delchini, Mathieu Martin, Brian Woods

Nuclear Technology / Volume 206 / Number 6 / June 2020 / Pages 862-894

Technical Paper / dx.doi.org/10.1080/00295450.2019.1667186

Developing Separate Effects Transient Test Experiments Using an Out-of-Pile Flowing Water Loop

Wade Marcum, Daniel LaBrier, Emory Brown, Yikuan Yan, Nicolas Woolstenhulme

Nuclear Technology / Volume 206 / Number 6 / June 2020 / Pages 895-910

Technical Paper / dx.doi.org/10.1080/00295450.2020.1720559

Benchmark Comparison of Experimental Data with Thermal-Hydraulic Codes RELAP5-3D and TRACE for a RIA Transient Scenario

Wade Marcum, Daniel LaBrier, Emory Brown, Colby Jensen, Yong-Joon Choi

Nuclear Technology / Volume 206 / Number 6 / June 2020 / Pages 911-923

Technical Paper / dx.doi.org/10.1080/00295450.2020.1713673

Miniature Sensor Irradiation Tests Under Steady-State and Transient Conditions at MIT Research Reactor (MITR) and Transient Reactor Test Facility (TREAT)

Kaichao Sun, David Carpenter, Michael Ames, Akshay J. Dave, Lin-Wen Hu

Nuclear Technology / Volume 206 / Number 6 / June 2020 / Pages 924-937

Technical Paper / dx.doi.org/10.1080/00295450.2019.1679564

Number 7

RETRACTED ARTICLE: Visualization and Integration of Images of Radioactive Substances as Point Cloud Data in 3-D Environment Models

Yuki Sato, Tatsuo Torii

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages v-xvi

Retracted Article / dx.doi.org/10.1080/00295450.2020.1722555

A Robust Cybersecurity Solution Platform Architecture for Digital Instrumentation and Control Systems in Nuclear Power Facilities

Fan Zhang, J. Wesley Hines, Jamie B. Coble

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 939-950

Technical Paper – Special section on the 2019 ANS Student Conference / dx.doi.org/10.1080/00295450.2019.1666599

Comparison of Multilayer Perceptron and Long Short-Term Memory for Plant Parameter Trend Prediction

Junyong Bae, Jeeyea Ahn, Seung Jun Lee

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 951-961

Technical Paper – Special section on the 2019 ANS Student Conference / dx.doi.org/10.1080/00295450.2019.1693215

Development of an Experimentally Validated MCNP6 Model for 11C Production via the 14N(p,α) Reaction Using a GE PETtrace Cyclotron

Amy Hall, Daniel A. Gum, Richard Ferrieri, John Brockman, James E. Bevins

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 962-976

Technical Paper – Special section on the 2019 ANS Student Conference / dx.doi.org/10.1080/00295450.2020.1740561

Quantification of Cardiac Dyssynchrony Entropy Implemented in a Commercial Nuclear Medicine Software Application

Natalie Baughan, Alexis Poitrasson-Rivière, Jonathan B. Moody, Benjamin C. Lee, Edward P. Ficaro

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 977-983

Technical Paper – Special section on the 2019 ANS Student Conference / dx.doi.org/10.1080/00295450.2019.1708142

A Direct Nondestructive Assay for the Pu of U/TRU Ingot in Pyroprocessing Using 244Cm Neutron Albedo Reactivity Technique and Its Error

Tae-Hoon Lee, Spencer Menlove, Howard O. Menlove, Hee-Sung Shin, Ho-Dong Kim

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 984-992

Regular Technical Paper / dx.doi.org/10.1080/00295450.2020.1743598

Performance Analysis of Silicon Carbide Composite Clad Uranium Carbide Fuel for a Long-Life Gas-Cooled Fast Reactor Under Normal Operation—Part I: Design Criteria and Material Data

Hangbok Choi, Robert W. Schleicher, John Bolin

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 993-1009

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1698936

Performance Analysis of Silicon Carbide Composite Clad Uranium Carbide Fuel for a Long-Life Gas-Cooled Fast Reactor Under Normal Operation—Part II: Modeling and Simulation

Hangbok Choi, John Bolin

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 1010-1018

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1699008

Benchmark of GOTHIC to EBR-II SHRT-17 and SHRT-45R Tests

J. W. Lane, J. M. Link, J. M. King, T. L. George, S. W. Claybrook

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 1019-1035

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1698896

A Probabilistic Model for Estimating the Life Expectancy of Used Nuclear Fuel Containers in a Canadian Geological Repository: Effects of Latent Defects and Repository Temperature

Allan K. Järvine, Alan G. Murchison, Peter G. Keech, Mahesh D. Pandey

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 1036-1058

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1700730

Highly Available Nuclear Power for Mission-Critical Applications

Jeremiah Doyle, Brandon Haley, Bill Galyean, Daniel T. Ingersoll

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 1059-1074

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1699382

Homography Transformation Correction Method for Position Error Generated in Readout Circuit Based on Resistive Network for the Compton Imaging System

Su-Jin Jeon, Jae-Sang Lee, Do-Hyun Kim, Seok-Ho Hong, Chun-Sik Lee, Young-Wan Choi

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 1075-1085

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1697175

An Overview of the Application of Pulsed Neutron Activation in Flow Measurements

M. R. Hadizadeh

Nuclear Technology / Volume 206 / Number 7 / July 2020 / Pages 1086-1094

Technical Note / dx.doi.org/10.1080/00295450.2019.1693214

Number 8

Nuclear Security Considerations for Space Nuclear Power: A Review of Past Programs with Recommendations for Future Criteria

Susan S. Voss

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1097-1108

Critical Review / dx.doi.org/10.1080/00295450.2019.1706378

Emergence of a Commercial Space Nuclear Enterprise

Jericho W. Locke, Bhavya Lal

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1109-1119

Technical Paper / dx.doi.org/10.1080/00295450.2019.1680080

Comparing the Effectiveness of Polymer and Composite Materials to Aluminum for Extended Deep Space Travel

Daniel K. Bond, Braden Goddard, Robert C. Singleterry, Jr., Sama Bilbao y León

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1120-1139

Technical Paper / dx.doi.org/10.1080/00295450.2019.1681221

LEU NTP Engine System Trades and Mission Options

C. Russell Joyner, II, Michael Eades, James Horton, Tyler Jennings, Timothy Kokan, Daniel J. H. Levack, Brian J. Muzek, Christopher B. Reynolds

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1140-1154

Technical Paper / dx.doi.org/10.1080/00295450.2019.1706982

Numerical Investigation and Parametric Study on Thermal-Hydraulic Characteristics of Particle Bed Reactors for Nuclear Thermal Propulsion

Yu Ji, ZeGuang Li, Jun Sun, ErSheng You, MingGang Lang, Lei Shi

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1155-1170

Technical Paper / dx.doi.org/10.1080/00295450.2020.1760703

Monte Carlo–Informed Decay Heat Model for Cermet LEU-NTP Systems

Andrew Denig, Michael Eades

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1171-1181

Technical Paper / dx.doi.org/10.1080/00295450.2020.1719798

Design Studies for the Optimization of 238Pu Production in NpO2 Targets Irradiated at the High Flux Isotope Reactor

Charles R. Daily, Joel L. McDuffee

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1182-1194

Technical Paper / dx.doi.org/10.1080/00295450.2019.1674594

Impact Temperature Determination for GPHS Safety Testing

Jonathan G. Teague, Roberta N. Mulford

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1195-1212

Technical Paper / dx.doi.org/10.1080/00295450.2019.1701345

Study on the Development of a Small ETG for the Korean Launch Vehicle’s Low Orbit Test

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

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1213-1223

Technical Paper / dx.doi.org/10.1080/00295450.2019.1682899

Temperature and Power Specific Mass Scaling for Commercial Closed-Cycle Brayton Systems in Space Surface Power and Nuclear Electric Propulsion Applications

Christopher G. Morrison

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1224-1239

Technical Paper / dx.doi.org/10.1080/00295450.2020.1738173

An Exploration of Mission Concepts That Could Utilize Small RPS

Young H. Lee, Alexander Austin, Brian K. Bairstow

Nuclear Technology / Volume 206 / Number 8 / August 2020 / Pages 1240-1251

Technical Note / dx.doi.org/10.1080/00295450.2020.1731403

Number 9

Turbulent Mixing Models and Other Mixing Coefficients in Subchannel Codes—A Review Part A: Single Phase

Aiguo Liu, Bao-Wen Yang, Bin Han, Xianlin Zhu

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1253-1295

Critical Review / dx.doi.org/10.1080/00295450.2020.1792753

A Novel Method for Predicting Power Transient CHF via the Heterogeneous Spontaneous Nucleation Trigger Mechanism

Emory Brown, Yikuan Yan, Wade R. Marcum

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1296-1307

Technical Paper / dx.doi.org/10.1080/00295450.2020.1724730

Toward Exascale: Overview of Large Eddy Simulations and Direct Numerical Simulations of Nuclear Reactor Flows with the Spectral Element Method in Nek5000

Elia Merzari, Paul Fischer, Misun Min, Stefan Kerkemeier, Aleksandr Obabko, Dillon Shaver, Haomin Yuan, Yiqi Yu, Javier Martinez, Landon Brockmeyer, Lambert Fick, Giacomo Busco, Alper Yildiz, Yassin Hassan

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1308-1324

Technical Paper / dx.doi.org/10.1080/00295450.2020.1748557

CFD Verification and Validation of Wire-Wrapped Pin Assemblies

Mathieu Martin, Daniel Leonard, R. Brian Jackson, K. Michael Steer

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1325-1336

Technical Paper / dx.doi.org/10.1080/00295450.2020.1727263

Benchmark Simulation of the Natural Convection Shutdown Heat Removal Test Facility Using SAM

B. Hollrah, M. Bucknor, D. Lisowski, Y. Hassan, R. Vaghetto, R. Hu

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1337-1350

Technical Paper / dx.doi.org/10.1080/00295450.2020.1745039

Severe Accident Phenomena: A Comparison Among the NuScale SMR, Other Advanced LWR Designs, and Operating LWRs

Scott J. Weber, Etienne M. Mullin

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1351-1360

Technical Paper / dx.doi.org/10.1080/00295450.2020.1756160

Challenges in Containment Thermal Hydraulics

E. Studer, D. Abdo, S. Benteboula, G. Bernard-Michel, B. Cariteau, N. Coulon, F. Dabbene, Ph. Debesse, S. Koudriakov, C. Ledier, J.-P. Magnaud, O. Norvez, J.-L. Widloecher, A. Beccantini, S. Gounand, J. Brinster

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1361-1373

Technical Paper / dx.doi.org/10.1080/00295450.2020.1731406

Dispersion of Surrogate LWR Fuel Experiments Under LOCA Conditions

G. D. Latimer, W. R. Marcum, W. F. Jones

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1374-1384

Technical Paper / dx.doi.org/10.1080/00295450.2020.1712158

Experimental Studies on Two-Layer Corium Heat Transfer in Light Water Reactor Lower Head in LIVE2D Facility

Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1385-1396

Technical Paper / dx.doi.org/10.1080/00295450.2020.1743102

Uniform Heated Scaled-Down Standard Fuel Block Test to Validate Core Thermofluid Analysis Code for Prismatic Gas-Cooled Reactor

Chan Soo Kim, Byung Ha Park, Eung Seon Kim, Min Hwan Kim

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1397-1408

Technical Paper / dx.doi.org/10.1080/00295450.2020.1735228

Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility

Marica Eboli, Alessandro Del Nevo, Nicola Forgione, Fabio Giannetti, Daniele Mazzi, Marco Ramacciotti

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1409-1420

Technical Paper / dx.doi.org/10.1080/00295450.2020.1749480

Comparison of Two Different Sized Small-Break LOCAs on the Passive Safety Injection Line Using SMART-ITL Data

Jin-Hwa Yang, Hwang Bae, Sung-Uk Ryu, Byong Guk Jeon, Sung-Jae Yi, Hyun-Sik Park

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1421-1435

Technical Paper / dx.doi.org/10.1080/00295450.2020.1775450

Thermal Design of the TREAT Facility

Bradley Heath, Colby Jensen

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1436-1448

Technical Paper / dx.doi.org/10.1080/00295450.2020.1725370

Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project

M. Pellegrini, L. Herranz, M. Sonnenkalb, T. Lind, Y. Maruyama, R. Gauntt, N. Bixler, A. Morreale, K. Dolganov, T. Sevon, D. Jacquemain, C. Journeau, J. H. Song, Y. Nishi, S. Mizokami

Nuclear Technology / Volume 206 / Number 9 / September 2020 / Pages 1449-1463

Technical Paper / dx.doi.org/10.1080/00295450.2020.1724731

Number 10

An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors

Cihang Lu, Zeyun Wu, Sarah Morgan, James Schneider, Mark Anderson, Liangyu Xu, Emilio Baglietto, Matthew Bucknor, Matthew Weathered, Sama Bilbao y Leon

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1465-1480

Technical Paper / dx.doi.org/10.1080/00295450.2020.1719799

Development of a New Method for Simulating Gas-to-Particle Conversion During Sodium Pool Fires in SFR Containment

Hongping Sun, Jian Deng, Dahuan Zhu, Yapei Zhang, Wenxi Tian, Suizheng Qiu, G. H. Su

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1481-1493

Technical Paper / dx.doi.org/10.1080/00295450.2020.1713672

Characteristic Analysis on Magnetic Field of Electromagnetic Flowmeter for Fast Reactor

Xuejing Li

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1494-1505

Technical Paper / dx.doi.org/10.1080/00295450.2019.1710432

Coupling of the Smoothed Particle Hydrodynamic Code Neutrino and the Risk Analysis Virtual Environment for Particle Spacing Optimization

Emerald D. Ryan, Chad L. Pope

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1506-1516

Technical Paper / dx.doi.org/10.1080/00295450.2019.1704576

Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 2

Takuya Yamashita, Ikken Sato, Takeshi Honda, Kenichiro Nozaki, Hiroyuki Suzuki, Marco Pellegrini, Takeshi Sakai, Shinya Mizokami

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1517-1537

Technical Paper / dx.doi.org/10.1080/00295450.2019.1704581

Thorium Utilization in Pressurized Water Reactors Using Bimetallic Thorium-Zirconium Alloy Cladding

Swaminathan Vaidyanathan

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1538-1552

Technical Paper / dx.doi.org/10.1080/00295450.2019.1706377

Visualization of Mass Transfer Between Source and Seeping Water in a Variable Aperture Fracture—Impact of Tracer Density

Helen Winberg-Wang, Ivars Neretnieks

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1553-1565

Technical Paper / dx.doi.org/10.1080/00295450.2020.1712951

Measurement of the Gas Velocity in a Water-Air Mixture in CROCUS Using Neutron Noise Techniques

Mathieu Hursin, Oskari Pakari, Gregory Perret, Pavel Frajtag, Vincent Lamirand, Imre Pázsit, Victor Dykin, Gabor Por, Henrik Nylén, Andreas Pautz

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1566-1583

Technical Paper / dx.doi.org/10.1080/00295450.2019.1701906

Enhancement of Thermal Conductivity of Bentonite Buffer Materials with Copper Wires/Meshes for High-Level Radioactive Waste Disposal

Yifeng Wang, Teklu Hadgu

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1584-1592

Technical Paper / dx.doi.org/10.1080/00295450.2019.1704577

Examining Practical Application Feasibility of Bismuth-Embedded SBA-15 for Gaseous Iodine Adsorption

Seong Woo Kang, Jae-Hwan Yang, Man-Sung Yim

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1593-1606

Technical Paper / dx.doi.org/10.1080/00295450.2020.1713680

New Compact Neutron Generator System for Multiple Applications

Ka-Ngo Leung

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1607-1614

Technical Note / dx.doi.org/10.1080/00295450.2020.1719800

Transient Studies on Low-Enriched-Uranium Core of Ghana Research Reactor–1 (GHARR-1)

Prince Amoah, Edward Shitsi, Emmanuel Ampomah-Amoako, Henry Cecil Odoi

Nuclear Technology / Volume 206 / Number 10 / October 2020 / Pages 1615-1624

Technical Note / dx.doi.org/10.1080/00295450.2020.1713681

Number 11

A Critical Review of Fluoride Salt Heat Transfer

Karl Britsch, Mark Anderson

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1625-1641

Critical Review / dx.doi.org/10.1080/00295450.2019.1682418

Heat-Pipe Heat Exchangers for Salt-Cooled Fission and Fusion Reactors to Avoid Salt Freezing and Control Tritium: A Review

Bahman Zohuri, Stephen Lam, Charles Forsberg

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1642-1658

Critical Review / dx.doi.org/10.1080/00295450.2019.1681222

Market Basis for Salt-Cooled Reactors: Dispatchable Heat, Hydrogen, and Electricity with Assured Peak Power Capacity

Charles W. Forsberg

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1659-1685

Technical Paper / dx.doi.org/10.1080/00295450.2020.1743628

A Stylized 3-D Benchmark Problem Set Based on the Pin-Fueled SmAHTR

K. Lisa Reed, Farzad Rahnema, Dingkang Zhang, Dan Ilas

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1686-1697

Technical Paper / dx.doi.org/10.1080/00295450.2020.1757962

Steady-State Thermal-Hydraulic Model for Fluoride-Salt-Cooled Small Modular High-Temperature Reactors

Sriram Chandrasekaran, Srinivas Garimella

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1698-1720

Technical Paper / dx.doi.org/10.1080/00295450.2020.1750274

Convective and Radiative Heat Transfer in Molten Salts

Sheng Zhang, Xiaodong Sun

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1721-1739

Technical Paper / dx.doi.org/10.1080/00295450.2020.1749481

Power Profile Reconstruction and Anomaly Detection Approach for FHRs Using Cerenkov Radiation

Jason A. Hearne, Pavel V. Tsvetkov

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1740-1750

Technical Paper / dx.doi.org/10.1080/00295450.2020.1746612

Corrosion Behavior of Pre-Carburized Hastelloy N, Haynes 244, Haynes 230, and Incoloy 800H in Molten FLiNaK

Kevin J. Chan, Preet M. Singh

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1751-1768

Technical Paper / dx.doi.org/10.1080/00295450.2020.1809311

Electrochemical Separation of Lanthanum Oxide in Molten FLiNaK Salt

Qiufeng Yang, Jianbang Ge, Yafei Wang, Jinsuo Zhang

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1769-1777

Technical Paper / dx.doi.org/10.1080/00295450.2020.1757976

Fusion Blankets and Fluoride-Salt-Cooled High-Temperature Reactors with Flibe Salt Coolant: Common Challenges, Tritium Control, and Opportunities for Synergistic Development Strategies Between Fission, Fusion, and Solar Salt Technologies

Charles Forsberg, Guiqiu (Tony) Zheng, Ronald G. Ballinger, Stephen T. Lam

Nuclear Technology / Volume 206 / Number 11 / November 2020 / Pages 1778-1801

Technical Paper / dx.doi.org/10.1080/00295450.2019.1691400

Number 12

Review of Candidate Techniques for Material Accountancy Measurements in Electrochemical Separations Facilities

Jamie B. Coble, Steven E. Skutnik, S. Nathan Gilliam, Michael P. Cooper

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1803-1826

Critical Review / dx.doi.org/10.1080/00295450.2020.1724728

Addressing Ambiguities in Constrained Sensitivity Analysis for Reactor Physics Problems

Jeongwon Seo, Hany Abdel-Khalik, Zoltan Perko

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1827-1839

Technical Paper / dx.doi.org/10.1080/00295450.2020.1721407

A Worker’s Fitness-for-Duty Status Identification Based on Biosignals to Reduce Human Error in Nuclear Power Plants

Young A Suh, Man-Sung Yim

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1840-1860

Technical Paper / dx.doi.org/10.1080/00295450.2020.1731405

Advanced MCNP Simulation of the Neutron and Photon Flux and Absorbed Dose Rates for the SLOWPOKE-2 Nuclear Reactor at the Royal Military College of Canada

J. C. Rook, K. P. Weber, E. C. Corcoran

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1861-1874

Technical Paper / dx.doi.org/10.1080/00295450.2020.1720557

Safety Enhancement Approach Against External Hazard on JSFR Reactor Building

Tomohiko Yamamoto, Atsushi Katoh, Yoshitaka Chikazawa, Hiroyuki Hara

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1875-1890

Technical Paper / dx.doi.org/10.1080/00295450.2020.1726155

Risk Reduction Assessment for Installing RCP Shutdown Seal

Hao-Ti Hsu, Ching-Han Chen, Chung-Kung Lo

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1891-1908

Technical Paper / dx.doi.org/10.1080/00295450.2020.1731404

Effects of Gamma Irradiation on Organic Membrane Materials

Rencheng Wang, Boxian Chen, Ding Chen, Xuan Zhao

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1909-1918

Technical Paper / dx.doi.org/10.1080/00295450.2020.1721406

Demonstration of Structural Integrity of Boiling Water Reactor Pressure Vessels Under Ultimate Response Guideline Operation

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

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1919-1931

Technical Paper / dx.doi.org/10.1080/00295450.2020.1724729

Assessment of Leaching Characteristics for Cerium and Cesium as Surrogates for Radioactive Materials

Riyadh M. Motny, Michael E. Woods, Supathorn Phongikaroon

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1932-1944

Technical Paper / dx.doi.org/10.1080/00295450.2020.1730672

Analysis on Transmutation of Long-Lived Fission Products from PWR Spent Fuel Using the 30-MW(thermal) RSG-GAS Reactor

M. Budi Setiawan, P. Made Udiyani, S. Kuntjoro, I. Husnayani, T. Surbakti

Nuclear Technology / Volume 206 / Number 12 / December 2020 / Pages 1945-1950

Technical Note / dx.doi.org/10.1080/00295450.2020.1720558

 

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