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Volume 85

Number 2

  • Table of Contents
  • Authors(Alireza Haghighat, Anthony J. Baratta, D. N. Sah, C. S. Viswanadham, Sunil Kumar, P. R. Roy, Ge-Ping Yu, Bau-Shei Pei, Ying-Pang Ma, Todd K. Campbell, Edgar Robert Gilbert, George D. White, Gregory F. Piepel, Bernard J. Wrona, John F. Geldard, Adolph L. Beyerlein, Masaki Suwa, Atsuyuki Suzuki, Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki, Wen-Shan Lin, Bau-Shei Pei, Chien-Hsiung Lee, I. A. Mudawwar, Thomas M. Parker, Richard J. Kohrt, Sue I. Dederer, Larry E. Hochreiter, Walter R. Schwarz, Chon-Kwo Tsai, Michael Y. Young, Khalid A. Al-Hussan, Tien-Ko Wang, Mohamed A. Obeid)

Gamma Transport Theory Analysis of the Three Mile Island Unit 2 Lower Head

Alireza Haghighat, Anthony J. Baratta

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 127-135

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34235

Electron Probe Microanalysis and Scanning Electron Microscopy of Deposits on the Inner Surface of Boiling Water Reactor Cladding

D. N. Sah, C. S. Viswanadham, Sunil Kumar, P. R. Roy

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 136-146

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34236

Reducing Scram Frequency by Relaxing Reactor Trip Setpoints at Maanshan Nuclear Power Station

Ge-Ping Yu, Bau-Shei Pei, Ying-Pang Ma

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 147-159

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34237

Oxidation Behavior of Nonirradiated UO2

Todd K. Campbell, Edgar Robert Gilbert, George D. White, Gregory F. Piepel, Bernard J. Wrona

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 160-171

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34238

CUSEP—A New Mathematical Model of Pulsed Column Contactors Using the Purex Process

John F. Geldard, Adolph L. Beyerlein

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 172-186

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT89-A34239

An Inference Model for Predicting a Pinching Effect in the Co-Decontamination Extraction Process in a Purex Fuel Reprocessing Plant

Masaki Suwa, Atsuyuki Suzuki

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 187-205

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT89-A34240

The Behavior of Iodine in a Simulated Spent-Fuel Solution

Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 206-212

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT89-A34241

A Theoretical Critical Heat Flux Model for Rod Bundles Under Pressurized Water Reactor Conditions

Wen-Shan Lin, Bau-Shei Pei, Chien-Hsiung Lee, I. A. Mudawwar

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 213-226

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34242

Application of Realistic Thermal-Hydraulic Methods for Pressurized Water Reactors with Upper Plenum Injection

Thomas M. Parker, Richard J. Kohrt, Sue I. Dederer, Larry E. Hochreiter, Walter R. Schwarz, Chon-Kwo Tsai, Michael Y. Young

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 227-237

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34243

Comparison of Gamma-Ray Heating Measurements Using Thermoluminescent Dosimeters with Calculations

Khalid A. Al-Hussan, Tien-Ko Wang, Mohamed A. Obeid

Nuclear Technology / Volume 85 / Number 2 / May 1989 / Pages 238-244

Technical Paper / Technique / dx.doi.org/10.13182/NT89-A34244