ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2018.1548220

Measurements of Total Hemispherical Emissivity of A508/A533B Alloy Steel

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

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 951-963

Regular Technical Paper / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2018.1554026

Fission Gas Release from Irradiated UO_2+x During Transient Annealing

A. R. Massih

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 992-1001

Technical Note / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2019.1585734