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Volume 155

Number 3

Development of Drywell Water Level Computational Aid and Application on Containment Flooding Strategy of Mark-III Nuclear Power Plant

Wei-Nian Su, Shih-Jen Wang, I-Ming Huang, Show-Chyuan Chiang

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 253-264

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3760

Full-Height Thermal-Hydraulic Scaling Analysis of Pb-Bi-Cooled Fast Reactor PEACER

Il S. Lee, Kune Y. Suh

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 265-281

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3761

Analysis of Pellet-Clad Mechanical Interaction Process of High-Burnup PWR Fuel Rods by RANNS Code in Reactivity-Initiated Accident Conditions

Motoe Suzuki, Toyoshi Fuketa, Hiroaki Saitou

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 282-292

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3762

An Assessment of Fuel Damage in Postulated Reactivity-Initiated Accidents

Ralph O. Meyer

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 293-311

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3763

A Linear Stability Analysis for Natural-Circulation Loops Under Supercritical Conditions

R. Jain, M. L. Corradini

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 312-323

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3764

Simulant Melt Experiments on In-Vessel Retention Through External Reactor Vessel Cooling

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Soon-Heung Chang

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 324-339

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3765

A System Design Study of a Fast Breeder Reactor Hydrogen Production Plant Using Thermochemical and Electrolytic Hybrid Process

Yoshitaka Chikazawa, Toshio Nakagiri, Mamoru Konomura, Shouji Uchida, Yoshihiko Tsuchiyama

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 340-349

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3766

A 16N/19O Monitor for Leak Detection in a Steam Generator

Shengyao Ding, Kun Xu, Xiaojian Huang, Zheng Wang

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 350-357

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3767

Calculation of Corrosion Rates of Alpha-Doped UO2

Hilbert Christensen

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 358-364

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT06-A3768

 
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