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Volume 196

Number 3

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

 
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