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Volume 167

Number 3

Hazard Assessment of the CIRCE Lead-Bismuth Experimental Facility in the ICE Configuration

Luciano Burgazzi

Nuclear Technology / Volume 167 / Number 3 / September 2009 / Pages 339-347

Technical Paper / Reactor Safety

Feasibility Study on a Simplified MOX Pellet Fabrication Process, the Short Process, for Fast Breeder Reactor Fuel

Koichi Asakura, Kentaro Takeuchi, Takayoshi Makino, Yoshiyuki Kato

Nuclear Technology / Volume 167 / Number 3 / September 2009 / Pages 348-361

Technical Paper / Fuel Cycle and Management

Use of Isotopically Modified Erbium in Advanced LWR Fuel

Fausto Franceschini, Bojan Petrovic

Nuclear Technology / Volume 167 / Number 3 / September 2009 / Pages 362-370

Technical Paper / Fuel Cycle and Management

Benchmark of Computational Fluid Dynamics Simulations Using Temperatures Measured Within Enclosed Vertical and Horizontal Arrays of Heated Rods

N. R. Chalasani, Pablo E. Araya, Miles Greiner

Nuclear Technology / Volume 167 / Number 3 / September 2009 / Pages 371-383

Technical Paper / Thermal Hydraulics

Benchmark of Natural Convection/Radiation Simulations Within an Enclosed Array of Horizontal Heated Rods

Pablo E. Araya, Miles Greiner

Nuclear Technology / Volume 167 / Number 3 / September 2009 / Pages 384-394

Technical Paper / Thermal Hydraulics

Calculation of Photon Exposure and Ambient Dose Slant-Path Buildup Factors for Radiological Assessment

Fritz G. Schirmers, Adam Davis, H. Omar Wooten, Donald J. Dudziak, Man-Sung Yim, David McNelis

Nuclear Technology / Volume 167 / Number 3 / September 2009 / Pages 395-409

Technical Paper / Radiation Protection

Ammonium Polyuranate Precipitation from Fluoride Solutions: An Experimental Study of the UO3-HF-NH3-H2O System as Applied in UF6 Processing

A. B. Rothman, D. G. Graczyk

Nuclear Technology / Volume 167 / Number 3 / September 2009 / Pages 410-420

Technical Paper / Reprocessing

 
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