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Volume 196

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 / 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

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