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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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!
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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A Second Generation Multiphase-CFD Framework Toward Predictive Modeling of DNB
Emilio Baglietto, Etienne Demarly, Ravikishore Kommajosyula, Nazar Lubchenko, Ben Magolan, Rosie Sugrue
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 1-22
Technical Paper | doi.org/10.1080/00295450.2018.1517528
The Implementation of an Activated Temperature-Dependent Wall Boiling Model in an Eulerian-Eulerian Computational Fluid Dynamics Approach for Predicting the Wall Boiling Process
Wei Ding, Eckhard Krepper, Uwe Hampel
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 23-32
Technical Paper | doi.org/10.1080/00295450.2018.1496693
High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors
E. Merzari, H. Yuan, A. Kraus, A. Obabko, P. Fischer, J. Solberg, S. Lee, J. Lai, M. Delgado, Y. Hassan
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 33-47
Technical Paper | doi.org/10.1080/00295450.2018.1490124
A Multiscale Approach Simulating Boiling in a Heated Pipe Including Flow Pattern Transition
T. Höhne, E. Krepper, D. Lucas, G. Montoya
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 48-56
Technical Paper | doi.org/10.1080/00295450.2018.1495025
CFD Modeling Development for DNB Prediction of Rod Bundle with Mixing Vanes Under PWR Conditions
Yiban Xu, Robert A. Brewster, Michael E. Conner, Zeses E. Karoutas, L. David Smith, III
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 57-67
Technical Paper | doi.org/10.1080/00295450.2018.1510265
Study on the Lateral Velocity and Vortex in a Spacer Grid
Bin Han, Bao-Wen Yang, Cen Wei, Yudong Zha
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 68-76
Technical Paper | doi.org/10.1080/00295450.2018.1506658
Multidimensional Hydraulic Solver Using Structured and Unstructured Meshes for the System Thermal-Hydraulic Code SPACE
Chan Eok Park, Jong Ho Choi, Gyu Cheon Lee, Sang Yong Lee
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 77-93
Technical Paper | doi.org/10.1080/00295450.2018.1501990
Pressure and Velocity Fluctuation in the Numerical Simulation of Bubble Detachment in a Venturi-Type Bubble Generator
Kangbei Cai, Yuchen Song, Jingjing Li, Dezhong Wang, Junlian Yin, Wei Liu, Hua Li
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 94-103
Technical Paper | doi.org/10.1080/00295450.2018.1479575
Energetic Liquid Droplet Boiling on High-Temperature Metal Surfaces
D. Moghul, J. C. Luxat
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 104-118
Technical Paper | doi.org/10.1080/00295450.2018.1515411
Development of Unstructured Mesh-Based Numerical Method for Sodium-Water Reaction Phenomenon
A. Uchibori, A. Watanabe, T. Takata, H. Ohshima
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 119-127
Technical Paper | doi.org/10.1080/00295450.2018.1499323
Uncertainty Analysis of the Conditional Exceedance Probability Calculation for a Probabilistically Significant SBO Sequence
Y. Du, H. X. Li, T. H. Liang, K. S. Liang
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 128-139
Technical Paper | doi.org/10.1080/00295450.2018.1494998
Development of a Pragmatic Approach to Model Input Uncertainty Quantification for BEPU Applications
Jinzhao Zhang, Adrien Dethioux, Andriy Kovtonyuk, Christophe Schneidesch
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 140-152
Technical Paper | doi.org/10.1080/00295450.2018.1516055
Evaluation of the PAR Mitigation System in Swiss PWR Containment Using the GOTHIC Code
Davide Papini, Michele Andreani, Pascal Steiner, Bojan Ničeno, Jens-Uwe Klügel, Horst-Michael Prasser
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 153-173
Technical Paper | doi.org/10.1080/00295450.2018.1505356
Sensitivity Analysis of LB-LOCA in Response to Proposed 10 CFR 50.46c New Rulemaking
Hongbin Zhang, Ronaldo Szilard, Ling Zou, Haihua Zhao
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 174-187
Technical Paper | doi.org/10.1080/00295450.2018.1496694
Thermal-Hydraulic Analysis of the LBE Spallation Target Head in JAEA
T. Wan, H. Obayashi, T. Sasa
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 188-199
Technical Paper | doi.org/10.1080/00295450.2018.1478591
Measurement of Type 304L Stainless Steel and 16MND5 Ferritic Steel Density and Surface Tension: Possible Impact for Stratified Molten Pool
N. Chikhi, P. Fouquart, J. Delacroix, P. Piluso
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 200-212
Technical Paper | doi.org/10.1080/00295450.2018.1486160
High-Resolution Velocity Field Measurements of Turbulent Round Free Jets in Uniform Environments
Sunming Qin, Benedikt Krohn, John Downing, Victor Petrov, Annalisa Manera
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 213-225
Technical Paper | doi.org/10.1080/00295450.2018.1470864
Effects of Substrate Materials and Surface Conditions on the Minimum Film-Boiling Temperature
Shikha A. Ebrahim, Ece Alat, Faruk A. Sohag, Valerie Fudurich, Shi Chang, Fan-Bill Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 226-238
Technical Paper | doi.org/10.1080/00295450.2018.1490122
Corium-Sodium and Corium-Water Fuel-Coolant-Interaction Experimental Programs for the PLINIUS2 Prototypic Corium Platform
Christophe Journeau, Laurence Aufore, Léonie Berge, Claude Brayer, Nathalie Cassiaut-Louis, Nicolas Estre, Frédéric Payot, Pascal Piluso, Jean-Christophe Prele, Shifali Singh, Magali Zabiégo, Eric Pluyette, Frédéric Serre, Béatrice Teisseire
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 239-247
Technical Paper | doi.org/10.1080/00295450.2018.1479580
Multiscaled Experimental Investigations of Corrosion and Precipitation Processes After Loss-of-Coolant Accidents in Pressurized Water Reactors
Stefan Renger, Sören Alt, Ulrike Gocht, Wolfgang Kästner, André Seeliger, Holger Kryk, Ulrich Harm
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 248-261
Technical Paper | doi.org/10.1080/00295450.2018.1499324
Development and Application of Molecular Tagging Velocimetry for Gas Flows in Thermal Hydraulics
Matthieu A. André, Ross A. Burns, Paul M. Danehy, Seth R. Cadell, Brian G. Woods, Philippe M. Bardet
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 262-271
Technical Paper | doi.org/10.1080/00295450.2018.1516954
Simultaneous PIV/PLIF and Pulsed Shadowgraphy Measurement of Gas-Liquid Flows in a Swirling Separator
Yalan Qian, Tingting Zhang, Jingjing Li, Yuchen Song, Junlian Yin, Dezhong Wang, Hua Li, Wei Liu
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 272-280
Technical Paper | doi.org/10.1080/00295450.2018.1486161
Study of Bottom Reflooding in a Narrow Rectangular Channel
Wei Xu, Jianhua Xia, Xiaojing Liu, Xu Cheng, Wei Zeng
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 281-296
Technical Paper | doi.org/10.1080/00295450.2018.1457887
Experimental Study of Blowdown Event in a PWR-Type Small Modular Reactor
Guanyi Wang, Yikuan Yan, Shanbin Shi, Zhuoran Dang, Xiaohong Yang, Mamoru Ishii
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 297-306
Technical Paper | doi.org/10.1080/00295450.2018.1493317
Rod Bundle Heat Transfer Thermal-Hydraulic Program
Stephen M. Bajorek, Fan-Bill Cheung
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 307-327
Technical Paper | doi.org/10.1080/00295450.2018.1510697
The Impact of Mixing Vane Arrangement on Mixing Coefficient β for Subchannel Analysis
Cen Wei, Bao-Wen Yang, Bin Han, Aiguo Liu
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 328-337
Technical Paper | doi.org/10.1080/00295450.2018.1510266
Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows
Xingang Zhao, Aaron J. Wysocki, Koroush Shirvan, Robert K. Salko
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 338-351
Technical Paper | doi.org/10.1080/00295450.2018.1507221
Application of the Improved Spacer Grid Model in Subchannel Analysis Code
Siying Dong, Wei Liu, Yang Liu, Jianqiang Shan
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 352-363
Technical Paper | doi.org/10.1080/00295450.2018.1491182
Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water
Pan Wu, David Novog
Nuclear Technology | Volume 205 | Number 1-2 | January-February 2019 | Pages 364-376
Technical Paper | doi.org/10.1080/00295450.2018.1495000
Variable and Assured Peak Electricity Production from Base-Load Light-Water Reactors with Heat Storage and Auxiliary Combustible Fuels
Charles W. Forsberg
Nuclear Technology | Volume 205 | Number 3 | March 2019 | Pages 377-396
Technical Paper | doi.org/10.1080/00295450.2018.1518555
Enhancing Electric Grid, Critical Infrastructure, and Societal Resilience with Resilient Nuclear Power Plants (rNPPs)
Sherrell R. Greene
Nuclear Technology | Volume 205 | Number 3 | March 2019 | Pages 397-414
Technical Paper | doi.org/10.1080/00295450.2018.1505357
Design and Operation of a Sensible Heat Peaking Unit for Small Modular Reactors
Konor Frick, J. Michael Doster, Shannon Bragg-Sitton
Nuclear Technology | Volume 205 | Number 3 | March 2019 | Pages 415-441
Technical Paper | doi.org/10.1080/00295450.2018.1491181
SHAKE-RoverD Framework for Nuclear Power Plants: A Streamlined Approach for Seismic Risk Assessment
Pegah Farshadmanesh, Tatsuya Sakurahara, Seyed Reihani, Ernie Kee, Zahra Mohaghegh
Nuclear Technology | Volume 205 | Number 3 | March 2019 | Pages 442-463
Technical Paper | doi.org/10.1080/00295450.2018.1494439
Investigations on Detecting Potential Nuclear Material Diversion from a Pyroprocessing Facility
Seung Min Woo, Heukjin Boo, Sunil S. Chirayath, Keunhong Jeong
Nuclear Technology | Volume 205 | Number 3 | March 2019 | Pages 464-473
Technical Paper | doi.org/10.1080/00295450.2018.1500074
The Effects of Plutonium Content and Self-Irradiation on Thermal Conductivity of Mixed Oxide Fuel
Yoshihisa Ikusawa, Kyoichi Morimoto, Masato Kato, Kosuke Saito, Masayoshi Uno
Nuclear Technology | Volume 205 | Number 3 | March 2019 | Pages 474-485
Technical Paper | doi.org/10.1080/00295450.2018.1494999
Benchmarking DRAGON/PARCS Against KRITZ and FFTF Measurements
Hangbok Choi, Myunghee Choi, Ryan Hon
Nuclear Technology | Volume 205 | Number 3 | March 2019 | Pages 486-505
Technical Paper | doi.org/10.1080/00295450.2018.1495001
A Comparison Study of Operator Preference and Performance for Analog Versus Digital Turbine Control Systems in Control Room Modernization
Ronald L. Boring, Thomas A. Ulrich, Roger Lew, Casey R. Kovesdi, Ahmad Al Rashdan
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 507-523
Technical Paper | doi.org/10.1080/00295450.2018.1509593
Analysis of a Large-Scale PWR In-Vessel Retention Device
Fei-Jan Tsai, Min Lee
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 524-541
Technical Paper | doi.org/10.1080/00295450.2018.1500831
Gnowee: A Hybrid Metaheuristic Optimization Algorithm for Constrained, Black Box, Combinatorial Mixed-Integer Design
James E. Bevins, R. N. Slaybaugh
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 542-562
Technical Paper | doi.org/10.1080/00295450.2018.1496692
Anisotropic Radiation-Induced Changes in Type 316L Stainless Steel Rods Built by Laser Additive Manufacturing
Jordan A. Evans, Scott A. Anderson, Eric J. Faierson, Delia Perez-Nunez, Sean M. McDeavitt
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 563-581
Technical Paper | doi.org/10.1080/00295450.2018.1502001
Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC
Youshi Zeng, Wenguan Liu, Wei Liu, Guanghua Wang, Yuan Qian, Nan Qian, Xiaoling Wu, Yu Huang, Shengwei Wu
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 582-591
Technical Paper | doi.org/10.1080/00295450.2018.1507200
Design, Fabrication, and Testing of Electrolytic Cell for Minimizing Simulated Active Waste
R. Puspalata, S. Sumathi, V. Balaji, S. Rangarajan, S. Velmurugan
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 592-604
Technical Paper | doi.org/10.1080/00295450.2018.1509586
Analysis of Korea’s PWR Spent Nuclear Fuel (SNF) Characteristics Evaluated from Existing SNF Inventories (1979–2015) and Projected SNF Inventories (2016–2089)
Ara Go, Daesik Yook, Kyuhwan Jeong, GyeongMi Kim, GunHee Jung, Ser Gi Hong
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 605-623
Technical Paper | doi.org/10.1080/00295450.2018.1500795
Establishing Outcrop Time Series at Various Depths in a Nonlinear Soil Column: An Iterative Approach
Robert E. Spears, Efe G. Kurt, Justin L. Coleman
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 624-636
Technical Note | doi.org/10.1080/00295450.2018.1507393
Particle Swarm Optimization Applied to the Nuclear Fuel Bundle Spacer Grid Spring Design
Victor C. Leite, Roberto Schirru, Miguel Mattar Neto
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 637-645
Technical Paper | doi.org/10.1080/00295450.2018.1516056
Estimation of the Release Time of Radio-Tellurium During the Fukushima Daiichi Nuclear Power Plant Accident and Its Relationship to Individual Plant Events
Sentaro Takahashi, Shigeto Kawashima, Akihide Hidaka, Sota Tanaka, Tomoyuki Takahashi
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 646-654
Technical Paper | doi.org/10.1080/00295450.2018.1521186
Modeling of Aerosol Fission Product Scrubbing in Experiments and in Integral Severe Accident Scenarios
Adolf Rýdl, Leticia Fernandez-Moguel, Terttaliisa Lind
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 655-670
Technical Paper | doi.org/10.1080/00295450.2018.1511213
Effects of Cerium Concentration and Solvent on Physical and Chemical Characterization of Rapid Setting Cement
Riyadh M. Motny, Supathorn Phongikaroon
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 671-683
Technical Paper | doi.org/10.1080/00295450.2018.1510698
Total Hemispherical Emissivity of Potential Structural Materials for Very High Temperature Reactor Systems: Alloy 617
Kyle L. Walton, Raymond K. Maynard, Tushar K. Ghosh, Robert V. Tompson, Dabir S. Viswanath, Sudarshan K. Loyalka
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 684-693
Technical Paper | doi.org/10.1080/00295450.2018.1521177
Experimental Study of High Energy Arcing Faults Using Medium Voltage Metalclad Switchgears
Hajime Kabashima, Fumio Kasahara
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 694-707
Technical Paper | doi.org/10.1080/00295450.2018.1518556
Conceptual Design of a Pilot-Scale Pyroprocessing Facility
Yoon Il Chang, Robert W. Benedict, Matthew D. Bucknor, Javier Figueroa, Joseph E. Herceg, Terry R. Johnson, Eugene R. Koehl, Richard M. Lell, Young Soo Park, Chad L. Pope, Stanley G. Wiedmeyer, Mark A. Williamson, James L. Willit, Reid James, Steve Meyers, Bryan Spaulding, John Underdahl, Mike Wolf
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 708-726
Technical Paper | doi.org/10.1080/00295450.2018.1513243
Demonstration of Hollow Fiber Membrane Technique for the Recovery of Plutonium from Analytical Laboratory Waste
S. Chaudhury, S. A. Ansari, P. K. Mohapatra, D. M. Noronha, J. S. Pillai, Ashutosh Srivastava, I. C. Pius
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 727-735
Technical Paper | doi.org/10.1080/00295450.2018.1510699
Design and Characterization of a Scintillator-Based Position-Sensitive Detector for Muon Imaging
Can Liao, Haori Yang, Zhengzhi Liu, Jason P. Hayward
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 736-747
Technical Paper | doi.org/10.1080/00295450.2018.1522885
FHR, HTGR, and MSR Pebble-Bed Reactors with Multiple Pebble Sizes for Fuel Management and Coolant Cleanup
Charles W. Forsberg, Per F. Peterson
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 748-754
Rapid Communication | doi.org/10.1080/00295450.2019.1573619
Evaluation of Non-Oxide Fuel for Fission-Based Nuclear Reactors on Spacecraft
Dakota J. Allen, Stuart R. Blair, Marshall G. Millett, Martin E. Nelson
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 755-765
Technical Paper | doi.org/10.1080/00295450.2018.1524228
Economically Feasible Mobile Nuclear Power Plant for Merchant Ships and Remote Clients
Luciano Ondir Freire, Delvonei Alves de Andrade
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 766-780
Technical Paper | doi.org/10.1080/00295450.2018.1546067
A Study of a Dose Constraint for Members of the Public Living Around Nuclear Power Plants in the United States
Tae Young Kong, Gamal Akabani, John W. Poston, Sr.
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 781-789
Technical Paper | doi.org/10.1080/00295450.2018.1546536
The Effect of Long-Term Oxidation on the Total Hemispherical Emissivity of Type 316L Stainless Steel
Faten N. Al Zubaidi, Kyle L. Walton, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 790-800
Technical Paper | doi.org/10.1080/00295450.2018.1542257
Surface Characterization of Depleted Uranium–Molybdenum to Determine Surface Coating Compatibility
Terry A. Ring, Byung Sang Choi, J. Paulo Perez, Brian Van Devener, Randy C. Polson, Douglas Crawford, Dennis Keiser, Daniel Wachs
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 801-818
Technical Paper | doi.org/10.1080/00295450.2018.1542252
Density-Driven Mass Transfer in Repositories for Nuclear Waste
Ivars Neretnieks, Helen Winberg-Wang
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 819-829
Technical Paper | doi.org/10.1080/00295450.2018.1537460
Analysis of Krypton-85 Legacy Waste Forms: Part II
Robert T. Jubin, Stephanie H. Bruffey
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 830-846
Technical Paper | doi.org/10.1080/00295450.2018.1523639
Dose Rate Evaluation for the ES-3100 Package with HEU Content Using MCNP, ADVANTG, Monaco, and MAVRIC
Pran K. Paul
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 847-866
Technical Paper | doi.org/10.1080/00295450.2018.1533319
Risk Management for Seal Leakage Modeling of Station Blackout Core Damage Frequency
Tai-Hung Wu, De-Cheng Chen
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 867-880
Technical Note | doi.org/10.1080/00295450.2018.1533320
Analysis of Velocity Distributions Across a Model Helical Coil Steam Generator
Michael S. Gorman, Marilyn Delgado, Saya Lee, Yassin A. Hassan
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 881-890
Technical Paper – Selected papers from the 2018 ANS Student Conference | doi.org/10.1080/00295450.2019.1600998
Development of an Experimental Routine for Electrochemical and Laser-Induced Breakdown Spectroscopy Composition Measurements of SmCl3 in LiCl-KCl Eutectic Salt Systems
Hunter Andrews, Supathorn Phongikaroon
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 891-904
Technical Paper – Selected papers from the 2018 ANS Student Conference | doi.org/10.1080/00295450.2018.1551988
Computer-Aided Star Shot Analysis for Linac Quality Assurance Testing
Gregory A. Szalkowski, Justin Roper
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 905-911
Technical Paper – Selected papers from the 2018 ANS Student Conference | doi.org/10.1080/00295450.2018.1533349
GPT-Free Sensitivity Analysis for Monte Carlo Models
Zeyun Wu, Jingang Liang, Xingjie Peng, Hany S. Abdel-Khalik
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 912-927
Regular Technical Paper | doi.org/10.1080/00295450.2018.1556062
Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code
William Boyd, Adam Nelson, Paul K. Romano, Samuel Shaner, Benoit Forget, Kord Smith
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 928-944
Regular Technical Paper | doi.org/10.1080/00295450.2019.1571828
Quantile Regressions Applied to Pressurized Water Reactor CHF Correlation Safety Criteria
Ross Pivovar, Ole Wieckhorst
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 945-950
Regular Technical Paper | doi.org/10.1080/00295450.2018.1548220
Measurements of Total Hemispherical Emissivity of A508/A533B Alloy Steel
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 951-963
Regular Technical Paper | doi.org/10.1080/00295450.2019.1573618
A Note on the Use of Uranine Tracer to Visualize Radionuclide Migration Experiments: Some Observations and Problems
Helen Winberg-Wang, Ivars Neretnieks, Mikko Voutilainen
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 964-977
Regular Technical Paper | doi.org/10.1080/00295450.2019.1573620
Design and Optimization of a Fast Neutron Radiography System Based on a High-Intensity D-T Fusion Neutron Generator
Jie Wang, Yanan Li, Yongfeng Wang, Taosheng Li, Zaodi Zhang
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 978-986
Regular Technical Paper | doi.org/10.1080/00295450.2019.1575122
MATLAB/FLUENT Model for Studying the Uncertainty Quantification of Spent Nuclear Fuel Heat Transfer
Imane Khalil, Quinn Pratt
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 987-991
Technical Note | doi.org/10.1080/00295450.2018.1554026
Fission Gas Release from Irradiated UO2+x During Transient Annealing
A. R. Massih
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 992-1001
Technical Note | doi.org/10.1080/00295450.2019.1568102
Machine-Learning Analysis of Moisture Carryover in Boiling Water Reactors
Haoyu Wang, Andrew Longman, J. Thomas Gruenwald, James Tusar, Richard Vilim
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1003-1020
Technical Paper – Special section on Big Data for Nuclear Power Plants | doi.org/10.1080/00295450.2019.1583957
Automated Identification of Causal Relationships in Nuclear Power Plant Event Reports
Yunfei Zhao, Xiaoxu Diao, Jonathon Huang, Carol Smidts
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1021-1034
Technical Paper – Special section on Big Data for Nuclear Power Plants | doi.org/10.1080/00295450.2019.1580967
Use of Dynamic Event Trees and Deep Learning for Real-Time Emergency Planning in Power Plant Operation
Ji Hyun Lee, Alper Yilmaz, Richard Denning, Tunc Aldemir
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1035-1042
Technical Paper – Special section on Big Data for Nuclear Power Plants | doi.org/10.1080/00295450.2018.1541394
Using Kernel Density Estimation to Detect Loss-of-Coolant Accidents in a Pressurized Water Reactor
Jacob A. Farber, Daniel G. Cole, Ahmad Y. Al Rashdan, Vaibhav Yadav
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1043-1052
Technical Paper – Special section on Big Data for Nuclear Power Plants | doi.org/10.1080/00295450.2018.1534484
A Data Model for Nuclear Power Plant Work Packages
Ahmad Al Rashdan, Vivek Agarwal
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1053-1061
Technical Paper – Special section on Big Data for Nuclear Power Plants | doi.org/10.1080/00295450.2019.1601469
Methods of Data Collection in Nuclear Power Plants
Ahmad Al Rashdan, Shawn St. Germain
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1062-1074
Rapid Communication – Special section on Big Data for Nuclear Power Plants | doi.org/10.1080/00295450.2019.1610637
Technology, Policy, and Market Drivers of (and Barriers to) Advanced Nuclear Reactor Deployment in the United States After 2030
John Bistline, Revis James, Andrew Sowder
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1075-1094
Regular Technical Paper | doi.org/10.1080/00295450.2019.1574119
Probabilistic Assessment of Peak Cladding Hoop Stress and Hydrogen Content of PWR SNF Rod Cladding
Elmar Eidelpes, Luis F. Ibarra, Ricardo A. Medina
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1095-1118
Regular Technical Paper | doi.org/10.1080/00295450.2019.1575127
Extraction of 137Cs from Acidic Feed by Centrifugal Contactors Using a Solution of Calix[4]arene-bis-1,2-benzo-crown-6 in Phenyltrifluoromethyl Sulphone
P. K. Mohapatra, P. K. Verma, D. R. Prabhu, D. R. Raut
Nuclear Technology | Volume 205 | Number 8 | August 2019 | Pages 1119-1125
Regular Technical Paper | doi.org/10.1080/00295450.2019.1575126
Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing
Charles Forsberg, Dean Wang, Eugene Shwageraus, Brian Mays, Geoff Parks, Carolyn Coyle, Maolong Liu
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1127-1142
Technical Paper | doi.org/10.1080/00295450.2019.1586372
Adsorption and Desorption of Tritium in Nuclear Graphite at 700°C: A Gas Chromatographic Study Using Hydrogen
Ke Deng, Mingjun Zhang, Xijun Wu, Qin Zhang, Guo Yang, Zhaowei Ma, Fei Wei, Guanghua Wang, Wei Liu
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1143-1153
Technical Paper | doi.org/10.1080/00295450.2019.1590076
Thermophysical Properties of Molten Stainless Steel Containing 5 mass % B4C
Hiroyuki Fukuyama, Hideo Higashi, Hidemasa Yamano
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1154-1163
Technical Paper | doi.org/10.1080/00295450.2019.1578572
Thermophysical Properties of Stainless Steel Containing 5 mass % B4C in the Solid Phase
Toshihide Takai, Tomohiro Furukawa, Hidemasa Yamano
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1164-1174
Technical Paper | doi.org/10.1080/00295450.2019.1607136
Highly Accurate Method for the Solution of Flow Coastdown in Pressurized Water Reactor
Sadia Khalid, Idrees Ahmad, Awais Zahur
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1175-1184
Technical Paper | doi.org/10.1080/00295450.2019.1580530
A New Two-Step Methodology for CANDU Analysis with the APEC-Assisted Nodal Equivalence Theory
Mohammad Abdul Motalab, Woosong Kim, Yonghee Kim
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1185-1204
Technical Paper | doi.org/10.1080/00295450.2019.1582942
Nonlinear Modeling of Ground Motions at Lotung LSST Site with Nested Surface Soil Constitutive Model
Robert Spears, Swetha Veeraraghavan, Justin Coleman
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1205-1218
Technical Paper | doi.org/10.1080/00295450.2019.1584492
Incremental Gains in Transuranic Activity Analysis in Air Samples for Radiological Emergency Response
S. Joseph Cope, Robert B. Hayes
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1219-1235
Technical Paper | doi.org/10.1080/00295450.2019.1590074
Electronic Stopping Powers of Formvar and Mylar Polymeric Materials for Heavy Ions: LSS Modified Theory and Monte Carlo Simulation
J. El Asri, O. El Bounagui, N. Tahiri, H. Erramli, A. Chetaine
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1236-1244
Technical Paper | doi.org/10.1080/00295450.2019.1590071
Estimation of Decay Heat in Ghana Research Reactor-1 Auxiliary Components Using ORIGEN-S: A Case Study
R. G. Abrefah, P. A. A. Essel
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1245-1250
Technical Note | doi.org/10.1080/00295450.2019.1585736
Development of Irradiation Test Devices for Transient Testing
Nicolas Woolstenhulme, Clint Baker, Colby Jensen, Daniel Chapman, Devin Imholte, Nate Oldham, Connie Hill, Spencer Snow
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1251-1265
Critical Review | doi.org/10.1080/00295450.2019.1590072
Safety Strategy and Update of the TREAT Facility Safety Basis
Douglas M. Gerstner, James R. Parry, David J. Broussard, Brandon L. Moon, Anthony W. LaPorta, Charles P. Forshee, Lawrence J. Harrison, Monty L. Conley
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1266-1289
Technical Paper | doi.org/10.1080/00295450.2018.1556993
Transient Reactor Test (TREAT) Facility Initial Approach to Restart Criticality Following Extended Standby Operation
Anthony W. LaPorta
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1290-1301
Technical Paper | doi.org/10.1080/00295450.2019.1565471
Transient Reactor Test (TREAT) Facility Restart Heat Balance Calibration and Rod Worth Measurements
Daniel T. Willcox, James R. Parry
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1302-1311
Technical Paper | doi.org/10.1080/00295450.2019.1590075
Analysis of Core Characterization Transients for TREAT Restart
Benjamin M. Chase, Anthony W. LaPorta, James R. Parry
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1312-1324
Technical Paper | doi.org/10.1080/00295450.2019.1585162
Restart of the Transient Reactor Test (TREAT) Facility Neutron Radiography Program
Shawn R. Jensen, Aaron E. Craft, Glen C. Papaioannou, Wyatt W. Empie, Blaine R. Ward, Lee A. Batt
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1325-1335
Technical Paper | doi.org/10.1080/00295450.2019.1605780
Metrology for Transient Reactor Characterization Using Uranium Wires
Thomas Holschuh, Scott Watson, David Chichester
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1336-1345
Technical Paper | doi.org/10.1080/00295450.2019.1599613
Transient Reactor Test Facility Advanced Transient Shapes
Thomas Holschuh, Nicolas Woolstenhulme, Benjamin Baker, John Bess, Cliff Davis, James Parry
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1346-1353
Technical Paper | doi.org/10.1080/00295450.2018.1559712
Development of Advanced Instrumentation for Transient Testing
Colby Jensen, Austin Fleming
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1354-1368
Technical Paper | doi.org/10.1080/00295450.2019.1627123
TREAT Restart Project
Bradley K. Heath, Cody C. Race
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1369-1377
Technical Note | doi.org/10.1080/00295450.2019.1589853
Transient Reactor Test (TREAT) Facility Design and Experiment Capability
Chad L. Pope, Colby B. Jensen, Douglas M. Gerstner, James R. Parry
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1378-1386
Technical Note | doi.org/10.1080/00295450.2019.1599615
A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams
Dawn E. Janney, Steven L. Hayes, Cynthia A. Adkins
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1387-1415
Critical Review | doi.org/10.1080/00295450.2019.1578573
Response Matrix Method–Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code
Jaakko Leppänen
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1416-1432
Technical Paper | doi.org/10.1080/00295450.2019.1603710
Application of Boron Carbide as Burnable Poison in Sodium Fast Reactors
H. Guo, P. Sciora, T. Kooyman, L. Buiron, G. Rimpault
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1433-1446
Technical Paper | doi.org/10.1080/00295450.2019.1620054
Application of Minor Actinides as Burnable Poisons in Sodium Fast Reactors
H. Guo, T. Kooyman, P. Sciora, L. Buiron
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1447-1459
Technical Paper | doi.org/10.1080/00295450.2019.1611304
Minor Actinide Transmutation in Supercritical-CO2-Cooled and Sodium-Cooled Fast Reactors with Low Burnup Reactivity Swings
Hoai-Nam Tran, Yasuyoshi Kato, Peng Hong Liem, Van-Khanh Hoang, Sy Minh Tuan Hoang
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1460-1473
Technical Paper | doi.org/10.1080/00295450.2019.1601470
Development of a Monte Carlo Modeling Approach to Determine the Enrichment of UF6 Typical Cylinders
Sayed A. El-Mongy, Kh. A. Allam
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1474-1479
Technical Paper | doi.org/10.1080/00295450.2019.1593012
Time Resolution of a Cs2LiYCl6:Ce3+ Detector Measured with a DRS4 Waveform Digitizer
Xianfei Wen, Andreas Enqvist
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1480-1487
Technical Paper | doi.org/10.1080/00295450.2019.1603503
Calculation of Heat Fluxes Exiting a CANDU Calandria During In-Vessel Retention
Robert David
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1488-1494
Technical Paper | doi.org/10.1080/00295450.2019.1597581
Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis
R. R. Romatoski, L. W. Hu
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1495-1512
Technical Paper | doi.org/10.1080/00295450.2019.1610686
Challenges in Application of BEPU for Risk Evaluations
Dumitru Serghiuta, John Tholammakkil
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1513-1528
Critical Review | doi.org/10.1080/00295450.2019.1570751
Best Estimate Plus Uncertainty (BEPU): Why It Is Still Not Widely Used
Evgeny Ivanov, Giovanni Bruna, Antonio Sargeni, Franck Dubois
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1529-1539
Technical Paper | doi.org/10.1080/00295450.2019.1627122
Verification and Validation and Uncertainty Quantification of Code Models
Tomasz Skorek
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1540-1553
Technical Paper | doi.org/10.1080/00295450.2019.1580532
The CASUALIDAD Method for Uncertainty Evaluation of Best-Estimate System Thermal-Hydraulic Calculations
A. Petruzzi
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1554-1566
Technical Paper | doi.org/10.1080/00295450.2019.1632092
RIPS, a Statistical Method for Characterizing the Limiting Scenario in a BEPU Approach
Jean-Christophe Lecoy, Jean-Yves Sauvage, Camille Charignon
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1567-1577
Technical Paper | doi.org/10.1080/00295450.2019.1580528
Applications of Multivariate Normal Bayesian Models in Nuclear Engineering
Axel Hoefer, Oliver Buss, Michael Schmid
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1578-1587
Technical Paper | doi.org/10.1080/00295450.2018.1560784
Advanced Methodology for Uncertainty Propagation in Computer Experiments with Large Number of Inputs
Bertrand Iooss, Amandine Marrel
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1588-1606
Technical Paper | doi.org/10.1080/00295450.2019.1573617
Quantified Validation with Uncertainty Analysis for Turbulent Single-Phase Friction Models
Nathan W. Porter, Vincent A. Mousseau, Maria N. Avramova
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1607-1617
Technical Paper | doi.org/10.1080/00295450.2018.1548221
Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core
Kaiyue Zeng, Jason Hou, Kostadin Ivanov, Matthew Anderson Jessee
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1618-1637
Technical Paper | doi.org/10.1080/00295450.2019.1580533
Global Sensitivity and Registration Strategy for Temperature Profile of Reflood Experiment Simulations
Grégory Perret, Damar Wicaksono, Ivor D. Clifford, Hakim Ferroukhi
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1638-1651
Technical Paper | doi.org/10.1080/00295450.2019.1591154
Proposal of a Statistical Evaluation Method for the Criticality of the Fukushima Daiichi Nuclear Power Plants
Yuichi Morimoto, Masanori Akaike, Satoshi Takeo, Hiromi Maruyama
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1652-1660
Technical Paper | doi.org/10.1080/00295450.2019.1580529
BEPU Method Applied to CFD Simulation of Mixing Flows
Andrej Prošek, Boštjan Končar, Matjaž Leskovar
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1661-1674
Technical Paper | doi.org/10.1080/00295450.2018.1562820
Cross-Section Generation Using TXT2NTAB Code for Uncertainty Propagation with Burnup Dependence
A. Labarile, C. Mesado, R. Miró, G. Verdú
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1675-1684
Technical Paper | doi.org/10.1080/00295450.2019.1631051
A Mutual Information–Based Experimental Design Framework to Use High-Fidelity Nuclear Reactor Codes to Calibrate Low-Fidelity Codes
Natalie Gordon, Lindsay Gilkey, Ralph C. Smith, Isaac Michaud, Brian Williams, Vincent Mousseau, Russell Hooper, Chris Jones
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1685-1696
Technical Paper | doi.org/10.1080/00295450.2019.1590073
Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF
Robert K. Salko, William D. Pointer, Marc-Oliver Delchini, William L. Gurecky, Kevin T. Clarno, Stuart R. Salttery, Victor Petrov, Annalisa Manera
Nuclear Technology | Volume 205 | Number 12 | December 2019 | Pages 1697-1706
Technical Paper | doi.org/10.1080/00295450.2019.1585734