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Volume 196

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT16-56