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Volume 24

Number 1

Table of Contents
Authors(A. Birkhofer, A. Schmidt, W. Werner, L. A. Zielke, R. H. Wilson, J. W. Dias, D. Okrent, R. C. Erdmann, Krishan Chitkara, Joel Weisman, A. J. Moorhead, J. R. DiStefano, R. E. McDonald, J. H. DeVan, R. L. Klueh, A. Notea, Y. Segal, R. B. Walton, E. I. Whitted, R. A. Forster, John P. Foster, Robert V. Strain, W. R. Sheets)

Comparison of Two- and Three-Dimensional Calculations of Super Prompt Critical Excursions

A. Birkhofer, A. Schmidt, W. Werner

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 7-12

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-A31456

Transient Critical Heat Flux and Spacer Grid Studies

L. A. Zielke, R. H. Wilson

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 13-19

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-A31457

Fission Gas Behavior in Fast Reactor Fuel Under Transient Power Conditions

J. W. Dias, D. Okrent, R. C. Erdmann

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 20-32

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-A31458

An Equilibrium Approach to Optimal in-Core Fuel Management for Pressurized Water Reactors

Krishan Chitkara, Joel Weisman

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 33-49

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT74-A31459

Fabrication Procedures for Unalloyed Molybdenum

A. J. Moorhead, J. R. DiStefano, R. E. McDonald

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 50-63

Technical Paper / Material / dx.doi.org/10.13182/NT74-A31460

The Effect of Oxygen on the Corrosion of Vanadium and V-20% Ti by Liquid Lithium

J. H. DeVan, R. L. Klueh

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 64-72

Technical Paper / Material / dx.doi.org/10.13182/NT74-A31461

A General Approach to the Design of Radiation Gauges

A. Notea, Y. Segal

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 73-80

Technical Paper / Instrument / dx.doi.org/10.13182/NT74-A31462

Gamma-Ray Assay of Low-Enriched Uranium Waste

R. B. Walton, E. I. Whitted, R. A. Forster

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 81-92

Technical Paper / Instrument / dx.doi.org/10.13182/NT74-A31463

Empirical Swelling Equations for Solution-Annealed Type 304 Stainless Steel

John P. Foster, Robert V. Strain

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 93-98

Technical Note / Material / dx.doi.org/10.13182/NT74-A31464

Digital Period Meter

W. R. Sheets

Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 99-101

Technical Note / Instrument / dx.doi.org/10.13182/NT74-A31465

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