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Number 1

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2019.1618130

Number 2

Table of Contents
Foreword: Selected papers from the 2018 International Topical Meeting on Advances in Thermal Hydraulics (ATH 2018) (Elia Merzari, Sama Bilbao y Leon, Sofiane Benhamadouche, John Luxat, Xu Cheng)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2019.1636589
Wall-Modeled Large Eddy Simulation of the Flow Through PWR Fuel Assemblies at Re_H = 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2019.1664199

Number 3

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2019.1632093

Number 4

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2019.1670009

Number 5

Table of Contents

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 | 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 | 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 | doi.org/10.1080/00295450.2019.1674581
Study on Sintering Kinetics of (Th_xCe_1-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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2019.1679564

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2020.1730673

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2019.1693214

Number 8

Table of Contents
Foreword: Selected papers from the 2019 Nuclear and Emerging Technologies for Space Topical Meeting (NETS 2019) (Christopher Morrison)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2020.1724731

Number 10

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2020.1713681

Number 11

Table of Contents
Foreword: Special issue on Salt-Cooled Reactors (Charles Forsberg, Farzad Rahnema)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2020.1720558

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