ANS / Publications / Journals / Nuclear Technology

The Once-Through Mode of Steam Generator Reflux Condensation in Loss-of-Coolant Accident Scenarios

Y. Liao, S. Guentay, D. Suckow

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 510-519

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12502

Potential for Steam Explosions Considering Droplet Solidification and Crust Stability

Michael Epstein, Hans K. Fauske, Wison Luangdilok

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 520-528

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12503

Flooding Experiments with Steam and Water in a Large-Diameter Vertical Tube

S. N. Ritchey, M. Solom, O. Draznin, I. Choutapalli, K. Vierow

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 529-537

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12504

URANS Simulation of Confined Parallel Jet Mixing

E. Merzari, H. Ninokata, R. Mereu, E. Colombo, F. Inzoli

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 538-552

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT10-148

Study of Heat Transfer and Mass Transfer in a Spray for Containment Application: Analysis of the Influence of Spray Temperature at the Injection Point

Pascal Lemaitre, Emmanuel Porcheron, Amandine Nuboer

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 553-571

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12506

Accident Management Actions in an Upper-Head Small-Break Loss-of-Coolant Accident with High-Pressure Safety Injection Failed

César Queral, Juan González-Cadelo, Gonzalo Jimenez, Ernesto Villalba

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 572-593

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12507

Benchmark on Hydrogen Distribution in a Containment Based on the OECD-NEA THAI HM-2 Experiment

S. Schwarz, K. Fischer, A. Bentaib, J. Burkhardt, J.-J. Lee, J. Duspiva, D. Visser, J. Kyttälä, P. Royl, J. Kim, P. Kostka, R. Liang

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 594-603

Technical Paper / NURETH-13 Special / Reactor Safety / dx.doi.org/10.13182/NT11-A12508

Effects of Break Size on Direct Vessel Injection Line Break Accidents of the ATLAS

Ki Yong Choi, Hyun Sik Park, Seok Cho, Kyoung Ho Kang, Nam Hyun Choi, Won Pil Baek, Yeon Sik Kim

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 604-618

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12509

Fragmentation of a Single Molten Metal Droplet Penetrating into Sodium Pool: Thermal and Hydrodynamic Effects on Fragmentation in Stainless Steel

Zhi-Gang Zhang, Ken-Ichiro Sugiyama

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 619-627

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12510

Sodium Experiments of Buoyancy-Driven Penetration Flow into Low-Power Subassemblies in a Sodium-Cooled Fast Reactor During Natural Circulation Decay Heat Removal

Hideki Kamide, Jun Kobayashi, Kenji Hayashi

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 628-640

Technical Paper / NURETH-13 Special / Fission Reactors / dx.doi.org/10.13182/NT11-A12511

Uncertainty of Relative Permeability to Describe Two-Phase Flow in Geological Disposal System

Yuichi Niibori, Joonhong Ahn, Hitoshi Mimura

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 641-651

Technical Paper / NURETH-13 Special / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A12512

Quantifying Phenomenological Importance in Best-Estimate Plus Uncertainty Analyses

Robert P. Martin

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 652-662

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT175-652

On the Establishment of a Web Portal for the Assessment of CFD in Reactor Safety Analysis

Brian L. Smith

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 663-680

Technical Paper / NURETH-13 Special / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12514

New Sensors for In-Pile Temperature Measurement at the Advanced Test Reactor National Scientific User Facility

J. L. Rempe, D. L. Knudson, J. E. Daw, K. G. Condie, S. Curtis Wilkins

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 681-691

Technical Paper / NURETH-13 Special / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT11-A12515

Development of Labyrinth-Type Sealing Devices for Prototype Fast Breeder Reactor Subassemblies

G. K. Pandey, I. Banerjee, G. Padmakumar, C. Anandababu, K. K. Rajan, G. Vaidyanathan, P. Kalyanasundaram, S. C. Chetal, Baldev Raj

Nuclear Technology / Volume 175 / Number 3 / September 2011 / Pages 692-699

Technical Note / NURETH-13 Special / Fission Reactors / dx.doi.org/10.13182/NT11-A12516