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Volume 22

Number 1

Table of Contents
Authors(Robert J. Teitel, A. P. Fraas, G. L. Kulcinski, R. G. Brown, R. G. Lott, P. A. Sanger, C. M. Logan, J. D. Anderson, Z. A. Munir, P. R. Okamoto, A. T. Santhanam, H. Wiedersich, A. Taylor, V. K. Sikka, J. Moteff, K. L. Merkle, D. J. Michel, C. Z. Serpan, Jr., H. H. Smith, A. G. Pieper, J. P. Moore, R. S. Graves, D. L. McElroy, T. G. Godfrey, D. L. McElroy, Z. L. Ardary, Don M. Parkin, Donald G. Schweitzer, A. B. Johnson, Jr., W. F. Vogelsang, S. Cantor, W. R. Grimes, R. A. Strehlow, H. C. Savage, K. Natesan, D. L. Smith)
Preface: Fusion Reactor Materials: 1973 ANS Winter Meeting(Robert J. Teitel)

Materials Problems in the Design of Magnetically Confined Plasma Fusion Reactors

A. P. Fraas

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 10-19

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16270

Radiation Damage Limitations in the Design of the Wisconsin Tokamak Fusion Reactor

G. L. Kulcinski, R. G. Brown, R. G. Lott, P. A. Sanger

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 20-35

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16271

The Relevance of Various Neutron Sources to Fusion-Reactor Radiation Effects

C.M. Logan, J. D. Anderson, Z. A. Munir

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 36-44

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16272

Impurity Redistribution Around Voids in lon-Bombarded Vanadium

P. R. Okamoto, A. T. Santhanam, H. Wiedersich, A. Taylor

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 45-51

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16273

Stability of the Defect State in Neutron-Irradiated Molybdenum

V. K. Sikka, J. Moteff

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 52-65

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16274

TEM Investigation of 14-MeV Neutron Damage

K. L. Merkle

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 66-78

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16275

Effect of Helium on the Fatigue Behavior of the Molybdenum-Base Alloy TZM at 900°C

D.J. Michel, C. Z. Serpan, Jr., H. H. Smith, A. G. Pieper

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 79-87

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16276

Thermal and Electrical Conductivities and Seebeck Coefficients of Unirradiated and Irradiated Graphites from 300 to 1000°K

J. P. Moore, R. S. Graves, D. L. McElroy

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 88-93

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16277

Thermal Conductivity of Oriented Fibrous Carbon Insulation from 300 to 1300°K in Nitrogen and Argon at One Atmosphere

T. G. Godfrey, D. L. McElroy, Z. L. Ardary

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 94-107

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16278

Effects of Neutron Irradiation on the Superconducting Properties of NbTi and Nb₃Sn Multifilamentary Composites

Don M. Parkin, Donald G. Schweitzer

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 108-114

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16279

Preliminary Assessment of Corrosion Product Transport in Fusion Reactors

A. B. Johnson, Jr., W. F. Vogelsang

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 115-119

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16280

Fused-Salt Corrosion and Its Control in Fusion Reactors

S. Cantor, W. R. Grimes

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 120-126

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16281

The Permeation of Hydrogen Isotopes Through Structural Metals at Low Pressures and Through Metals with Oxide Film Barriers

R. A. Strehlow, H. C. Savage

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 127-137

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16282

Effectiveness of Tritium Removal from a CTR Lithium Blanket by Cold Trapping Secondary Liquid Metals Na, K, and NaK

K. Natesan, D. L. Smith

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Pages 138-150

Technical Paper / Fusion Reactor Materials / Material / dx.doi.org/10.13182/NT74-A16283

The Elements of Nuclear Power

Rocco A. Fazzolare

Nuclear Technology / Volume 22 / Number 1 / April 1974 / Page 151

Department / Fusion Reactor Materials / Book Review / dx.doi.org/10.13182/NT74-A16284