ANS / Publications / Journals / Nuclear Technology

The Effects of Fast Flux Irradiation on the Mechanical Properties and Dimensional Stability of Stainless Steel

T. T. Claudson, R. W. Barker, R. L. Fish

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 10-23

Fuel Cladding Model / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28723

An Analysis of Fast Neutron Effects on Void Formation And Creep in Metals

S.D. Harkness, J. A. Tesk, Che-Yu Li

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 24-30

Fuel Cladding Model / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28724

New Correlations Involving the Low-Cycle Fatigue and Short-Term Tensile Behavior of Irradiated and Unirradiated 304 and 316 Stainless Steel

J. B. Conway, J. T. Berling, R. H. Stentz

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 31-39

Fuel Cladding Model / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28725

Theoretical Analysis of Cladding Stresses and Strains Produced by Expansion of Cracked Fuel Pellets

J. H. Gittus, D. A. Howl, H. Hughes

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 40-46

Fuel Cladding Model / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28726

Axial Ratchetiing of Fuel Under Pressure Cycling Conditions

Eliot Duncombe, Ivan Goldberg

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 47-59

Fuel Cladding Model / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28727

Crash-A Computer Program for the Evaluation of the Creep and Plastic Behavior of Fuel-Pin Sheaths

M. Guyette

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 60-69

Fuel Cladding Model / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28728

A Three-Dimensional Method for Design Studies of Xenon-Induced Spatial Power Oscillations

R. C. Kern, W. C. Coppersmith, Z. R. Rosztoczy

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 70-82

Reactor / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28729

The Nuclear Performance of Fusion Reactor Blankets

D. Steiner

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 83-92

Reactor / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28730

Calculational Models for Fast Reactor Fuel-Cycle Analysis

Thomas J. Hirons, R. Douglas O'Dell

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 93-106

Fuel / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28731

The Effects of Contaminants in Methane as a Proportional Tube Counting Gas

F. E. Armstrong, W. D. Howell, D. W. Whitlock

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 107-111

Instrument / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28732

Evaluation of Cdte as an Integral Gamma-Ray Counter

H. H. Nichols

Nuclear Technology / Volume 9 / Number 1 / July 1970 / Pages 112-119

Instrument / Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material / dx.doi.org/10.13182/NT70-A28733