ANS / Publications / Journals / Nuclear Technology

Introduction to the Annular Fuel Special Issue

Mujid S. Kazimi

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Page 1

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT160-1-1

Annular Fuel for High-Power-Density Pressurized Water Reactors: Motivation and Overview

Pavel Hejzlar, Mujid S. Kazimi

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 2-15

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT160-2-15

Thermal-Hydraulic Design of High-Power-Density Annular Fuel in PWRs

Dandong Feng, Pavel Hejzlar, Mujid S. Kazimi

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 16-44

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3882

Safety Analysis of High-Power-Density Annular Fuel for PWRs

Dandong Feng, Paolo Morra, Ramu Sundaram, Won-Jae Lee, Pradip Saha, Pavel Hejzlar, Mujid S. Kazimi

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 45-62

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3883

High-Performance Annular Fuel Reactor Physics and Fuel Management

Zhiwen Xu, Yasuyuki Otsuka, Pavel Hejzlar, Mujid S. Kazimi, Michael J. Driscoll

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 63-79

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3884

Fertile-Free Annular Fuel for Plutonium Recycling

Eugene Shwageraus, Pavel Hejzlar, Mujid S. Kazimi

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 80-99

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3885

High-Power-Density Annular Fuel: Manufacturing Viability

Edward Lahoda, Herbert Feinroth, Marcelo Salvatore, Diego O. Russo, Holly Hamilton

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 100-111

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3886

High-Power-Density Annular Fuel for Pressurized Water Reactors: Manufacturing Costs and Economic Benefits

Edward Lahoda, Jason Mazzoccoli, Julien Beccherle

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 112-134

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3887

Thermomechanical Performance of High-Power-Density Annular Fuel

Yi Yuan, M. S. Kazimi, P. Hejzlar

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 135-149

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3888

Irradiation Testing of High-Power-Density Vibropacked Annular Fuel

Gordon Kohse, David Carpenter, Yi Yuan, Pavel Hejzlar, Mujid Kazimi

Nuclear Technology / Volume 160 / Number 1 / October 2007 / Pages 150-168

Technical Paper / Annular Fuel / dx.doi.org/10.13182/NT07-A3889

Study on Leak Rate of Gas Medium in Leak-Before-Break Technique - I: Experimental Studies

Zhengming Zhang, Shuyan He

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 170-177

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3890

Study on Leak Rate of Gas Medium in Leak-Before-Break Technique - II: Theoretical Studies

Zhengming Zhang, Shuyan He

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 178-186

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3891

Direct Simulation, Monte Carlo, Multicomponent, Aerosol Dynamics: Coagulation, Deposition, and Source Reinforcement

Geethpriya Palaniswaamy, Sudarshan K. Loyalka

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 187-204

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT160-187

Boron Transport Model with Physical Diffusion for RELAP5

Jordi Freixa, Francesc Reventós, Carme Pretel, Lluís Batet

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 205-215

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3893

Feasibility Study of a Passive DHR System with Heat Transfer Enhancement Mechanism in a Lead-Cooled Fast Reactor

Jae-Hyuk Eoh, Seyun Kim, Sang-Ji Kim, Seong-O Kim

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 216-232

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3894

The Synergetic Effects of Nuclear-Assisted Gas Turbine Power Cycles

Yong Hoon Jeong, Mujid S. Kazimi

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 233-243

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3895

Radiochemical Analysis in Fuel Integrity Evaluation

Chien C. Lin, J. H. Chao

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 244-250

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT07-A3896

Molecular Dynamics Simulations of Graphite at High Temperatures

Brian D. Hehr, Ayman I. Hawari, Victor H. Gillette

Nuclear Technology / Volume 160 / Number 2 / November 2007 / Pages 251-256

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT07-A3897

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