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Volume 153

Number 2

On an Improved Design of a Fluidized Bed Nuclear Reactor - I: Design Modifications and Steady-State Features

Alexander Agung, Danny Lathouwers, Tim H. J. J. van der Hagen, Hugo van Dam, Christopher C. Pain, Anthony J. H. Goddard, Matthew D. Eaton, Jefferson L. M. A. Gomes, Bryan Miles, Cassiano R. E. de Oliveira

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 117-131

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3694

A Physics Study on Thorium Fuel Recycling in a CANDU Reactor Using Dry Process Technology

Hangbok Choi, Chang Je Park

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 132-145

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3695

Recycle of Transuranium Elements in Light Water Reactors for Reduction of Geological Storage Requirements

E. Fridman, E. Shwageraus, A. Galperin, M. Todosow

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 146-163

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3696

Progress of the DUPIC Fuel Compatibility Analysis - II: Thermal Hydraulics

Joo Hwan Park, Jee-Won Park, Hangbok Choi, Myung Seung Yang

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 164-174

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3697

Experiment and RELAP5 Analysis for the Downcomer Boiling of APR1400 Under LBLOCA Reflood Phase

Dong Won Lee, Hee Cheon No, Eu Hwak Lee, Seung Jong Oh, Chul-Hwa Song

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 175-183

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3698

Modeling of a Power Conversion System with RELAP5-3D/K and Associated Application to the Feedwater Blowdown Licensing Analysis for the ABWR Containment Design

Thomas K. S. Liang, Chung-Yu Yang, Liang-Che Dai, Fu-Kuang Ko

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 184-196

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3699

Computational Fluid Dynamics Predicting the Distributions of Thinning Locations on the Shell Wall of Feedwater Heaters

Y.-M. Ferng, J. H. Hsieh, C. D. Horng

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 197-207

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3700

Simulant Melt Experiments on Thermal and Metallurgical Performance of the In-Vessel Core Catcher

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, K.Y. Suh, F. B. Cheung, J. L. Rempe

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 208-223

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3701

Breeding of 242mAm in a Fast Reactor

Y. Ronen, M. Aboudy, D. Regev

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 224-233

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3702

The Temperature Feature on the Step-Up Process of the Hydraulic Control Rod Driving System

Yanhua Zheng, Hanliang Bo, Duo Dong

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 234-239

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3703