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Volume 196

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Number 1

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT15-117

Number 2

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT16-31

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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