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Volume 85

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

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