ANS / Publications / Journals / Nuclear Technology

Relative Proliferation Risks for Different Fuel Cycle Arrangements

Meng Yue, Lap-Yan Cheng, Robert A. Bari

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 1-17

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT09-A4058

Development and Validation of a Porous-Medium Computational Fluid Dynamics Model for a Fast Boron Shutdown System

Timothy J. Drzewiecki, Brian L. Mount, Martin Lopez de Bertodano

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 18-31

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A4059

Validation of the TASS/SMR and MARS Codes for a Natural-Circulation Experiment at the VISTA Facility

Y. J. Chung, S. H. Yang, H. K. Kim, M. K. Chung, K. K. Kim

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 32-42

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A4060

Experimental and Numerical Analysis of Natural Convection in Geometrically Modeled Core Catcher of the Liquid-Metal-Cooled Fast Reactor

Anil Kumar Sharma, Sanjay Kumar Das, J. Harvey

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 43-52

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A4061

A Benchmark System for Comparing Reliability Modeling Approaches for Digital Instrumentation and Control Systems

Jason Kirschenbaum, Paolo Bucci, Michael Stovsky, Diego Mandelli, Tunc Aldemir, Michael Yau, Sergio Guarro, Eylem Ekici, Steven A. Arndt

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 53-95

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT09-A4062

Low-Burnup Irradiation Behavior of Fast Reactor Metal Fuels Containing Minor Actinides

Hirokazu Ohta, Takanari Ogata, Takeshi Yokoo, Michel Ougier, Jean-Paul Glatz, Bruno Fontaine, Laurent Breton

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 96-110

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT09-A4063

Accelerator-Based Target Design and Optimization Driven by High-Energy Electron Beams and Proton Beams for the Analysis of Neutron Generation Characteristics

Yaxi Liu, Man-Sung Yim, David McNelis

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 111-123

Technical Paper / Accelerators / dx.doi.org/10.13182/NT09-A4064

Elemental Analysis of Neutron-Induced Gamma-Ray Spectra for Detection of Hazardous Materials

Bin Liu, Xuefeng Lv, Shiliang Zhou, Ying Wu

Nuclear Technology / Volume 165 / Number 1 / January 2009 / Pages 124-131

Technical Note / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT09-A4065

On an Improved Design of a Fluidized Bed Nuclear Reactor - II: Linear Stability and Transient Analysis

Alexander Agung, Danny Lathouwers, Tim H. J. J. van der Hagen, Hugo van Dam, Christopher C. Pain

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 133-144

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT09-A4081

Transient Heat Transfer Characteristics Between Molten Fuel and Steel with Steel Boiling in the CABRI-TPA2 Test

Hidemasa Yamano, Yu-Ichi Onoda, Yoshiharu Tobita, Ikken Sato

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 145-165

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A4082

Current Status of Knowledge of the Fluoride Salt (FLiNaK) Heat Transfer

J. Ambrosek, M. Anderson, K. Sridharan, T. Allen

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 166-173

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT165-166

Modeling and Simulation of a CANDU Reactor for Control System Design and Analysis

Hooman Javidnia, Jin Jiang, Majid Borairi

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 174-189

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT09-A4084

Actinide Recovery Experiments with Bench-Scale Liquid Cadmium Cathode in Real Fission Product-Laden Molten Salt

Shelly X. Li, S. D. Herrmann, K. M. Goff, M. F. Simpson, R. W. Benedict

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 190-199

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT09-A4085

Preparing High-Loaded Potassium Cobalt Hexacyanoferrate/Silica Composite for Radioactive Wastewater Treatment

Hai-Di Liu, Fu-Zhi Li, Xuan Zhao, Gui-Chun Yun

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 200-208

Technical Paper / Decontamination/decommissioning / dx.doi.org/10.13182/NT09-A4086

Evaluation of Transportation and Acceptance Strategies Associated with the Potential Yucca Mountain Waste Management System

Leah Spradley, Mark Abkowitz, James H. Clarke

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 209-222

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT09-A4087

Actinide Migration in Fractures of Granite Host Rock: Laboratory and In Situ Investigations

Bernhard Kienzler, Peter Vejmelka, Jürgen Römer, Dieter Schild, Mats Jansson

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 223-240

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT09-A4088

Effect of the Intermediate Cooling Process on the Behavior of the Zircaloy-4 Cladding After a High-Temperature Oxidation

Jun Hwan Kim, Byoung Kwon Choi, Yong Hwan Jeong, Seung Jin Oh

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 241-248

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT09-A4089

Measurement and Application of Paralysis Factor for Improved Detector Dead-Time Characterization

Amol Patil, Shoaib Usman

Nuclear Technology / Volume 165 / Number 2 / February 2009 / Pages 249-256

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT09-A4090

Studies on Chemical Speciation of Sodium Aerosols Produced in Sodium Fire

V. Subramanian, P. Sahoo, N. Malathi, R. Ananthanarayanan, R. Baskaran, B. Saha

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 257-269

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT09-A4100

Technology Gap Analysis on Sodium-Cooled Reactor Fuel-Handling System Supporting Advanced Burner Reactor Development

Yoshitaka Chikazawa, Mitchell Farmer, Christopher Grandy

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 270-292

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT09-A4101

The ASTEC Integral Code for Severe Accident Simulation

J. P. van Dorsselaere, C. Seropian, P. Chatelard, F. Jacq, J. Fleurot, P. Giordano, N. Reinke, B. Schwinges, H. J. Allelein, W. Luther

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 293-307

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT09-A4102

Toward an Atomistically Informed Fuel Performance Code: Thermal Properties Using FRAPCON and Molecular Dynamics Simulation

Daniel A. Vega, Taku Watanabe, Susan B. Sinnott, Simon R. Phillpot, James S. Tulenko

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 308-312

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT09-A4103

Numerical Simulation of Free-Surface Vortices

Elia Merzari, Hisashi Ninokata, Sheng Wang, Emilio Baglietto

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 313-320

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A4104

Thermal Analysis of a Fuel-Handling System for Sodium-Cooled Reactor with Minor Actinide-Bearing Metal Fuel

Yoshitaka Chikazawa, Christopher Grandy

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 321-332

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A4105

Integrated Methodology for Thermal-Hydraulic Code Uncertainty Analysis with Application

Mohammad Pourgol-Mohamad, Mohammad Modarres, Ali Mosleh

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 333-359

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT165-333

Removing Acetic Acid from a UREX+ Waste Stream: A Review of Technologies

Jessica A. Mitchell, R. M. Counce, J. S. Watson, B. B. Spencer, G. D. Del Cul

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 360-369

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT09-A4107

Assessment of a High-Throughput Electrorefining Concept for a Spent Metallic Nuclear Fuel - II: Electrohydrodynamic Analysis and Validation

J. H. Lee, K. H. Oh, Y. H. Kang, S. C. Hwang, H. S. Lee, J. B. Shim, E. H. Kim, S. W. Park

Nuclear Technology / Volume 165 / Number 3 / March 2009 / Pages 370-379

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT09-A4108