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Volume 85

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Number 1

Table of Contents
Authors(Ronald R. Winget, Stephen E. Binney, Alla J. M. Bakir, Sadao Hattori, Hiroshi Sasakawa, Norihiko Handa, Timo A. Vanttola, Markku K. Rajamäki, Krishna Vinjamuri, Edgar M. Feldman, Carlan K. Mullen, Robert C. Hill, Bryan A. Chin, E. Robert Gilbert, Aamir Husain, Robert E. Woodley, Robert E. Einziger, H. Craig Buchanan, T. Sampat Sridhar, Ahmad G. Solomah, S. M. Sami, T. Duong, Hisayoshi Mitamura, Seiichiro Matsumoto, William J. Buykx, Shingo Tashiro)

Point Beach Nuclear Plant Secondary In-Service Inspection Project and Badness Factor Program

Ronald R. Winget

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 7-11

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34222

Design and Development of a Personal-Computer-Based Reactivity Meter for a Research Reactor

Stephen E. Binney, Alla J. M. Bakir

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 12-21

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34223

Human Error Analysis Related to Structural Reliability

Sadao Hattori, Hiroshi Sasakawa, Norihiko Handa

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 22-32

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34224

One-Dimensional Considerations on the Initial Phase of the Chernobyl Accident

Timo A. Vanttola, Markku K. Rajamäki

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 33-74

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34225

Results and Analyses of Dry Rod Consolidation Using Westinghouse Spent-Fuel Assemblies

Krishna Vinjamuri, Edgar M. Feldman, Carlan K. Mullen, Robert C. Hill

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 48-56

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34226

Prediction of Maximum Allowable Temperatures for Dry Storage of Zircaloy-Clad Spent Fuel in Inert Atmosphere

Bryan A. Chin, E. Robert Gilbert

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 57-65

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34227

A Process for Decontaminating Stainless Steels to Release Limits

Aamir Husain

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 66-73

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT89-A34228

Measurement of the Oxidation of Spent Fuel Between 140 and 225°C

Robert E. Woodley, Robert E. Einziger, H. Craig Buchanan

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 74-88

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT89-A34229

SYNROC-FA Waste Form for Immobilization of Amine High-Level Liquid Waste: Process Development and Product Characterization

T. Sampat Sridhar, Ahmad G. Solomah

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 89-97

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34230

A Transient Model for Predicting Nonhomogeneous Nonequilibrium Critical Two-Phase Flows

S. M. Sami, T. Duong

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 98-108

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34231

Fabrication of Curium-Doped SYNROC for an Alpha Radiation Stability Test

Hisayoshi Mitamura, Seiichiro Matsumoto, William J. Buykx, Shingo Tashiro

Nuclear Technology / Volume 85 / Number 1 / April 1989 / Pages 109-117

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34232

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

Number 3

Table of Contents
Authors(Karen H. Koger, M. Jonathan Haire, Brett L. Humphrys, Jay F. Manneschmidt, Keiichi Setoguchi, Ryodai Nakai, Kazunori Sasaki, Naotaka Terashita, Takamichi Ogino, Makoto Osaki, Akira Kanagawa, Jan-Li Wang, Jay F. Kunze, L. C. Lewis, J. P. Henscheid, Mukesh Tayal, Lorne D. Macdonald, Erl Kohn, Walter P. Dovigo, T. Sampat Sridhar, Michael P. Manahan, Xiangdong Feng, Ian L. Pegg, Aaron Barkatt, Pedro B. Macedo, Samuel J. Cucinell, Shantao Lai, R. K. S. Rathore, P. Munshi, P. Arora, S. D. Malik, A. K. Vaish, K. S. Singh, U. Singh)

The Centralized Reliability Data Organization (CREDO) Assessment of Critical Component Unavailability in Liquid-Metal Reactors

Karen H. Koger, M. Jonathan Haire, Brett L. Humphrys, Jay F. Manneschmidt, Keiichi Setoguchi, Ryodai Nakai

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 251-258

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34247

The Development of the Fast-Running Simulation Pressurized Water Reactor Plant Analyzer Code (NUPAC-1)

Kazunori Sasaki, Naotaka Terashita, Takamichi Ogino

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 259-273

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34248

Performance of High-Efficiency Particulate Air Filters Under Severe Conditions

Makoto Osaki, Akira Kanagawa

Nuclear Technology / Volume 85 / Number 3 / June 1989 / Pages 274-284

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34249