ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Sep 2021
Jul 2021
Latest Journal Issues
Nuclear Science and Engineering
October 2021
Nuclear Technology
Fusion Science and Technology
August 2021
Latest News
IAEA boosts projections for nuclear power’s potential growth
The International Atomic Energy Agency has revised upward its projections regarding the potential growth of nuclear power’s capacity for electricity generation over the next three decades. The upward revision is the first by the IAEA since the Fukushima Daiichi accident in 2011.
Released last week, the 148-page report, Energy, Electricity and Nuclear Power Estimates for the Period up to 2050, provides detailed glimpses into possible nuclear futures in North America; Latin America and the Caribbean; Northern, Western, and Southern Europe; Eastern Europe; Africa; Western Asia, Southern Asia, and Central and Eastern Asia; Southeastern Asia; and Oceania. Global and regional nuclear power projections are presented as low and high cases.
Jump to:
Making Construction Cost Estimate of Nuclear Power Plants Credible: Assessing Impact of Unknown Unknowns
Giovanni Maronati, Bojan Petrovic
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 1-18
Technical Paper | dx.doi.org/10.1080/00295450.2020.1738829
Hiroshima and Nagasaki Verification of an Unstructured Mesh-Based Transmutation Toolkit
Tucker C. McClanahan, Tim Goorley, John Auxier, II
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 19-36
Technical Paper | dx.doi.org/10.1080/00295450.2020.1741295
Radiation Source Localization Using Surrogate Models Constructed from 3-D Monte Carlo Transport Physics Simulations
Paul R. Miles, Jared A. Cook, Zoey V. Angers, Christopher J. Swenson, Brian C. Kiedrowski, John Mattingly, Ralph C. Smith
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 37-53
Technical Paper | dx.doi.org/10.1080/00295450.2020.1738796
Effect of Upstream Parameters on Two-Phase Critical Flow Leakage Characteristics
Hongdong Zhen, Songtao Yin, Lei Zhang, Ningning Wang, Bo Xu, Haijun Wang
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 54-61
Technical Paper | dx.doi.org/10.1080/00295450.2020.1739994
Practicality of Analytical Solutions for Heat Transfer in Circular Systems in the Infinite Region to Describe Temperatures Due to Disposal of Heat-Decaying Nuclear Waste
John B. Case, Harris R. Greenberg, Bruce E. Kirstein
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 62-73
Technical Paper | dx.doi.org/10.1080/00295450.2020.1747837
Research on the Cognitive Reliability Model of DCS+SOP in the Ling’ao Phase II Nuclear Power Plant’s Main Control Room
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
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
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
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
