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Volume 205

Number 1-2 | Number 3 | Number 4 | Number 5 | Number 6 | Number 7

Number 1-2

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

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

Number 3

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

Number 4

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

Number 5

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

Number 6

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

Number 7

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 UO2+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

 
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