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Full-Core Evaluation of Uranium-Based Fuels Augmented with Small Amounts of Thorium in Pressure Tube Heavy Water Reactors
Ashlea V. Colton, Blair P. Bromley
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 1-12
Technical Paper | doi.org/10.13182/NT16-70
Basis for Fluoride Salt–Cooled High-Temperature Reactors with Nuclear Air-Brayton Combined Cycles and Firebrick Resistance-Heated Energy Storage
Charles Forsberg, Per F. Peterson
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 13-33
Technical Paper | doi.org/10.13182/NT16-28
Thermal-Hydraulic Analyses of Transportable Fluoride Salt–Cooled High-Temperature Reactor with CFD Modeling
Chenglong Wang, Kaichao Sun, Lin-Wen Hu, Suizheng Qiu, G. H. Su
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 34-52
Technical Paper | doi.org/10.13182/NT15-42
Radiation Heat Transfer in the Molten Salt FLiNaK
Ethan S. Chaleff, Thomas Blue, Piyush Sabharwall
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 53-60
Technical Paper | doi.org/10.13182/NT16-52
Secondary Sodium Fire Measures in JSFR
Yoshitaka Chikazawa, Atsushi Katoh, Tomohiko Yamamoto, Shigenobu Kubo, Shuji Ohno, Mikinori Iwasaki, Hiroyuki Hara, Yoshio Shimakawa, Hiroshi Sakaba
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 61-73
Technical Paper | doi.org/10.13182/NT15-131
Capability Enhancement of MATRIX Electromagnetic Pump Analysis Code by Including Thermal Analysis
Ana Da Silva, Pradip Saha, Eric P. Loewen
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 74-88
Technical Paper | doi.org/10.13182/NT16-55
Corrosion Properties of Zircaloy-4 and M5 Under Simulated PWR Water Conditions
Akira Shibata, Yoshiaki Kato, Taketoshi Taguchi, Masatoshi Futakawa, Katsuhiro Maekawa
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 89-99
Technical Paper | doi.org/10.13182/NT16-54
High-Temperature Corrosion Testing of Uranium Silicide Surrogates
K. Urso, K. Sridharan, B. J. Jaques, G. Alanko, D. P. Butt, M. Meyer, P. Xu, B. Tyburska-Püschel
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 100-110
Technical Paper | doi.org/10.13182/NT15-155
Sample Preparation Techniques for Grain Boundary Characterization of Annealed TRISO-Coated Particles
M. L. Dunzik-Gougar, I. J. van Rooyen, C. M. Hill, T. Trowbridge, J. Madden, J. Burns
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 111-120
Technical Paper | doi.org/10.13182/NT15-129
Diffusion and Sorption Properties of Some Sorbing Nuclides onto Granodiorite in a Modified Through-Diffusion Setup
Chung-Kyun Park, Min-Hoon Baik, Yong-Kwon Koh
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 121-129
Technical Paper | doi.org/10.13182/NT15-148
Creep Evaluation of Traditional and Nuclear Power Plant High-Temperature Components, Using Small Pin-Loaded One-Bar and Two-Bar Specimens
Balhassn S. M. Ali, Terry Y. P. Yuen, Mohamed Saber
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 130-140
Technical Paper | doi.org/10.13182/NT15-117

Number 2

Table of Contents
Foreword: Special issue on the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (W. David Pointer, Xiaodong Sun)

United States Department of Energy Severe Accident Research Following the Fukushima Daiichi Accidents
M. T. Farmer, M. Corradini, J. Rempe, R. Reister, D. Peko
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 141-148
Technical Paper | doi.org/10.13182/NT16-42
Severe Accident Research in Japan After the Fukushima Daiichi Nuclear Power Station Accident
Jun Sugimoto
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 149-160
Technical Paper | doi.org/10.13182/NT16-21
Past and Future Research at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident
Didier Jacquemain, Didier Vola, Renaud Meignen, Jean-Michel Bonnet, Florian Fichot, Emmanuel Raimond, Marc Barrachin
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 161-174
Technical Paper | doi.org/10.13182/NT16-13
Status and Challenges of Nuclear Thermal Hydraulics Research in China for Water-Cooled Reactors
X. Cheng, Y. H. Yang
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 175-186
Technical Paper | doi.org/10.13182/NT15-163
10 CFR 50.46c Rulemaking: A Novel Approach in Restating the LOCA Problem for PWRs
Cesare Frepoli, Joseph P. Yurko, Ronaldo H. Szilard, Curtis L. Smith, Robert Youngblood, Hongbin Zhang
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 187-197
Technical Paper | doi.org/10.13182/NT16-66
Benchmark Study of the Accident at the Fukushima Daiichi NPS: Best-Estimate Case Comparison
M. Pellegrini, K. Dolganov, L. E. Herranz, H. Bonneville, D. Luxat, M. Sonnenkalb, J. Ishikawa, J. H. Song, R. O. Gauntt, L. Fernandez Moguel, F. Payot, Y. Nishi
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 198-210
Technical Paper | doi.org/10.13182/NT16-63
ATHLET-CD/COCOSYS Analyses of Severe Accidents in Fukushima Daiichi Units 2 and 3: German Contribution to the OECD/NEA BSAF Project, Phase 1
M. Sonnenkalb, S. Band
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 211-222
Technical Paper | doi.org/10.13182/NT16-25
Towards a Consolidated Approach for the Assessment of Evaluation Models of Nuclear Power Reactors
A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 223-237
Technical Paper | doi.org/10.13182/NT16-47
TRACE/PARCS Analysis of Anticipated Transient Without Scram with Instability for a MELLLA+ BWR/5
L.-Y. Cheng, J. S. Baek, A. Cuadra, A. Aronson, D. Diamond, P. Yarsky
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 238-247
Technical Paper | doi.org/10.13182/NT16-29
Evaluation of Passive Containment Cooling with an Advanced Water Film Model in a Lumped-Parameter Code
Xi Huang, Xu Cheng, Walter Klein-Heßling
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 248-259
Technical Paper | doi.org/10.13182/NT16-67
GOTHIC 8.1 Benchmark to ThAI Facility Experiment with Steam-Helium Stratification
T. M. Moore, T. L. George
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 260-269
Technical Paper | doi.org/10.13182/NT16-17
RoverD: Use of Test Data in GSI-191 Risk Assessment
Ernie Kee, John Hasenbein, Alex Zolan, Phil Grissom, Seyed Reihani, Zahra Mohaghegh, Fatma Yilmaz, Bruce Letellier, Vera Moiseytseva, Rodolfo Vaghetto, David Imbaratto, Tatsuya Sakurahara
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 270-291
Technical Paper | doi.org/10.13182/NT16-34
MELCOR and GOTHIC Analyses of a Large Dry PWR Containment to Support Resolution of GSI-191
B. Beeny, R. Vaghetto, K. Vierow, Y. A. Hassan
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 292-302
Technical Paper | doi.org/10.13182/NT16-36
Development of Heat Transfer Model Package for Horizontal U-Shaped Heat Exchanger Submerged in Pool of Passive Safety System
Seong-Su Jeon, Soon-Joon Hong, Hyoung-Kyu Cho, Goon-Cherl Park
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 303-318
Technical Paper | doi.org/10.13182/NT16-22
Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility
Q. Lv, H. C. Lin, S. Shi, X. Sun, R. N. Christensen, T. E. Blue, G. Yoder, D. Wilson, P. Sabharwall
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 319-337
Technical Paper | doi.org/10.13182/NT16-41
Experimental Evaluation of Helical-Type Sodium-to-Air Heat Exchanger Performance for Thermal Sizing Design Code Validation
S. Yeom, J. Eoh, J. Hong, J.-Y. Jeong
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 338-345
Technical Paper | doi.org/10.13182/NT16-30
Temperature Profiles and Mixing in a Natural-Circulation Cooling Facility via Distributed Optical Sensors
C. Tompkins, M. Corradini, M. Anderson
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 346-354
Technical Paper | doi.org/10.13182/NT16-26
Validation and Application of the REKO-DIREKT Code for the Simulation of Passive Autocatalytic Recombiner Operational Behavior
Ernst-Arndt Reinecke, Stephan Kelm, Paul-Martin Steffen, Michael Klauck,Hans-Josef Allelein
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 355-366
Technical Paper | doi.org/10.13182/NT16-7
A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Autocatalytic Recombiners
Ernst-Arndt Reinecke, Ahmed Bentaïb, Jürgen Dornseiffer, Daniel Heidelberg, Franck Morfin, Pascal Zavaleta, Hans-Josef Allelein
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 367-376
Technical Paper | doi.org/10.13182/NT16-4
Development and Verification of the Dynamic System Code THERMO-T for Research Reactor Accident Analysis
Marat Margulis, Erez Gilad
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 377-395
Technical Paper | doi.org/10.13182/NT16-23
Uncertainty Quantification of Calculated Temperatures for Advanced Gas Reactor Fuel Irradiation Experiments
Binh T. Pham, Grant L. Hawkes, Jeffrey J. Einerson
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 396-407
Technical Paper | doi.org/10.13182/NT16-31

Number 3

Table of Contents
Foreword: Special issue on the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (W. David Pointer, Xiaodong Sun)
Technical Reviewers, 2016
Vol. 196 Author Index
Vol. 196 Subject Index

Nuclear Safety and Thermal Hydraulics: Personal Thoughts and Some Recent Progress
George Yadigaroglu, Djamel Lakehal
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 409-420
Technical Paper | doi.org/10.13182/NT16-49
Some Issues and Challenges in Advanced Thermal-Hydraulic Safety Research
Chul-Hwa Song
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 421-445
Technical Paper | doi.org/10.13182/NT16-91
Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Melt Spreading
M. T. Farmer, K. R. Robb, M. W. Francis
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 446-460
Technical Paper | doi.org/10.13182/NT16-44
Key Findings and Remaining Questions in the Areas of Core-Concrete Interaction and Debris Coolability
M. T. Farmer, C. Gerardi, N. Bremer, S. Basu
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 461-474
Technical Paper | doi.org/10.13182/NT16-43
Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core-Concrete Interaction
K. R. Robb, M. T. Farmer, M. W. Francis
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 475-488
Technical Paper | doi.org/10.13182/NT16-48
Core Melt Composition at Fukushima Daiichi: Results of Transient Simulations with ASTEC
H. Bonneville, L. Carenini, M. Barrachin
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 489-498
Technical Paper | doi.org/10.13182/NT16-27
Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station
F. Nagase, R. O. Gauntt, M. Naito
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 499-510
Technical Paper | doi.org/10.13182/NT16-10
Phenomenological Modeling Approach to Anisotropic Ablation in Molten Core–Concrete Interactions
Kyoung M. Kang, Michael L. Corradini
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 511-523
Technical Paper | doi.org/10.13182/NT15-157
Core Melt Stabilization Concepts for Existing and Future LWRs and Associated Research and Development Needs
Manfred Fischer, Sevostian V. Bechta, Vladimir V. Bezlepkin, Ryoichi Hamazaki, Alexei Miassoedov
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 524-537
Technical Paper | doi.org/10.13182/NT16-19
Fuel-Coolant Interaction Test Results Under Different Cavity Conditions
S. W. Hong, Y. S. Na, S. H. Hong, J. H. Song
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 538-552
Technical Paper | doi.org/10.13182/NT16-9
Critical Power and Void Fraction Prediction of Tight Bundle Designs
Xingang Zhao, Koroush Shirvan, Yingwei Wu, Mujid S. Kazimi
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 553-567
Technical Paper | doi.org/10.13182/NT16-45
Velocity Measurements and Turbulent Dispersion in Annular Liquid Film Flows in BWR Subchannels with Spacers
Abhishek Saxena, Jan Eiholzer, Harshank Agarwal, Horst-Michael Prasser
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 568-587
Technical Paper | doi.org/10.13182/NT16-20
A New Lumped Thermal Resistance Heat Transfer Model for Fuel Pin Structure
Shisheng Wang, Andrei Rineiski, Liancheng Guo
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 588-597
Technical Paper | doi.org/10.13182/NT16-5
Development of Passive In-Core Cooling System for Nuclear Safety Using Hybrid Heat Pipe
Kyung Mo Kim, Yeong Shin Jeong, In Guk Kim, In Cheol Bang
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 598-613
Technical Paper | doi.org/10.13182/NT16-32
Experimental Investigation of Air-Water CCFL in the Pressurizer Surge Line of AP1000
Jiangtao Yu, Dalin Zhang, Leitai Shi, Zhiwei Wang, Shixian Yan, Bo Dong, Wenxi Tian, G. H. Su, Suizheng Qiu
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 614-640
Technical Paper | doi.org/10.13182/NT16-24
Design of the Compact Integral Effects Test Facility and Validation of Best-Estimate Models for Fluoride Salt–Cooled High-Temperature Reactors
N. Zweibaum, Z. Guo, J. C. Kendrick, P. F. Peterson
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 641-660
Technical Paper | doi.org/10.13182/NT16-15
Study of Convection Heat Transfer in a Very High Temperature Reactor Flow Channel: Numerical and Experimental Results
Francisco I. Valentín, Narbeh Artoun, Ryan Anderson, Masahiro Kawaji, Donald M. McEligot
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 661-673
Technical Paper | doi.org/10.13182/NT16-46
Thermal Shrinkage–Based Model for Predicting the Voids During Solidification of Lead
Niranjan Gudibande, Kannan Iyer
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 674-683
Technical Paper | doi.org/10.13182/NT16-40
MAAP-MELCOR Crosswalk Phase 1 Study
David L. Luxat, Donald A. Kalanich, Joshua T. Hanophy, Randall O. Gauntt, Richard M. Wachowiak
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 684-697
Technical Paper | doi.org/10.13182/NT16-57
EPRI MAAP5 Fukushima Daiichi Analysis
David L. Luxat, Jeff R. Gabor, Richard M. Wachowiak, Rosa L. Yang
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 698-711
Technical Paper | doi.org/10.13182/NT16-56

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