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Home / Publications / Journals / Nuclear Technology / Volume 160 / Number 3

Volume 160

Number 3

Feasibility of Designing the Encapsulated Nuclear Heat Source Reactor with Negative Void Reactivity Feedback

Tsuyoshi Okawa, Ehud Greenspan

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 257-278

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3898

On the Fuel and Coolant Interaction Behavior of Partially Oxidized Corium

J. H. Song, J. H. Kim, S. W. Hong, B. T. Min, S. H. Hong

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 279-293

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT07-A3899

Validation of RCS Bleed-and-Feed Strategy for the SAMG of the Kuosheng Nuclear Power Plant

I Ming Huang, Yuh Ming Ferng, Shih Jen Wang

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 294-307

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT07-A3900

Initial Size Distribution of Sodium Combustion Aerosol

V. Subramanian, R. Baskaran

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 308-313

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT07-A3901

Simulation of the Internal Flows of an Inlet Diffuser Assembly for the CANDU-6 Moderator Analysis

Churl Yoon, Joo Hwan Park

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 314-324

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3902

Use of Fuel Assembly/Backfill Gas Effective Thermal Conductivities to Predict Basket and Fuel Cladding Temperatures Within a Rail Package During Normal Transport

Miles Greiner, Kishore Kumar Gangadharan, Mithun Gudipati

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 325-336

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3903

Influence of Alpha Radiolysis of Water on UO2 Matrix Alteration: Chemical/Transport Model

A. Poulesquen, C. Jégou

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 337-345

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT07-A3904

Experimental and Numerical Study on the Flow Distribution and the Pressure Drop of a Tubular Fuel

Jong-Hark Park, Hee-Taek Chae, Cheol Park, Heonil Kim

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 346-351

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3905

Calculated Reduction of the Residual Adsorbent Mass Requiring Long-Term Storage in Radioactive Waste Processing by Magnetic Separation

James H. P. Watson, Patrick Foss-Smith, Ray Lidzey

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 352-360

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT07-A3906

Physical Property Modeling of Concentrated Cesium Eluate Solutions - Part I: Derivation of Models

A. S. Choi, R. A. Pierce, T. B. Edwards, T. B. Calloway

Nuclear Technology / Volume 160 / Number 3 / December 2007 / Pages 361-373

Technical Note / Radioisotopes / dx.doi.org/10.13182/NT07-A3907

 

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