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Volume 39

Number 2

Table of Contents
Authors(P. V. Balakrishnan, G. M. Allison, Kin Wah Wong, Vijay K. Dhir, W. E. Kastenberg, M. Dalle Donne, S. Dorner, G. Schumacher, K. Takeuchi, P. Verbeek, H. Tbbe, N. Hoppe, B. Steinmetz, R. F. Mattas, D. L. Smith, D. R. Duncan, F. Lee, J. Matolich, Jr., J. Moteff, Prodyot Roy, Douglas N. Rodgers, Prodyot Roy, Bruce E. Bugbee)
Economics of Long-Distance Transmission, Storage, and Distribution of Heat from Nuclear Plants with Existing and Newer Techniques(Peter H. Margen)

Some In-Reactor Loop Experiments on Corrosion Product Transport and Water Chemistry

P. V. Balakrishnan, G. M. Allison

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 105-120

Technical Paper / Reactor / dx.doi.org/10.13182/NT78-A32072

A Mechanistic Study of Fuel Freezing, Channel Plugging, and Continued Coolability During Fast Reactor Overpower Excursions

Kin Wah Wong, Vijay K. Dhir, W. E. Kastenberg

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 121-137

Technical Paper / Reactor / dx.doi.org/10.13182/NT78-A32073

Development Work for a Borax Internal Core-Catcher for a Gas-Cooled Fast Reactor

M. Dalle Donne, S. Dorner, G. Schumacher

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 138-154

Technical Paper / Reactor / dx.doi.org/10.13182/NT78-A32074

Hydraulic Force Calculation with Hydro-Structural Interactions

K. Takeuchi

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 155-166

Technical Paper / Reactor / dx.doi.org/10.13182/NT78-A32075

Liquid-Metal Fast Breeder Reactor Fuel Rod Performance and Modeling at High Burnup

P. Verbeek, H. Tbbe, N. Hoppe, B. Steinmetz

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 167-185

Technical Paper / Fuel / dx.doi.org/10.13182/NT78-A32076

Model for Life-Limiting Properties of Fusion Reactor Structural Materials

R. F. Mattas, D. L. Smith

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 186-198

Technical Paper / Material / dx.doi.org/10.13182/NT78-A32077

Effect of Prior Irradiation Creep on the Subsequent Burst Strength of 20% Cold-Worked Type 316 Stainless-Steel Cladding

D. R. Duncan

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 199-206

Technical Paper / Material / dx.doi.org/10.13182/NT78-A32078

Irradiation Temperature Determination by Electrical Resistivity Measurements

F. Lee, J. Matolich, Jr., J. Moteff

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 207-212

Technical Paper / Material / dx.doi.org/10.13182/NT78-A32079

Hydrogen Burden from the Steam Side Corrosion in Sodium-Heated Steam Generators

Prodyot Roy, Douglas N. Rodgers

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 213-215

Technical Note / Analysis / dx.doi.org/10.13182/NT78-A32080

Electrochemical Oxygen Sensor for Measurement of Oxygen in Liquid Sodium

Prodyot Roy, Bruce E. Bugbee

Nuclear Technology / Volume 39 / Number 2 / July 1978 / Pages 216-218

Technical Note / Analysis / dx.doi.org/10.13182/NT78-A32081

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