American Nuclear Society

/Create an Account

Home

Home / Publications / Journals / Nuclear Technology / Volume 57 / Number 1

Volume 57

Number 1

Table of Contents
Authors(E. M. Dean, H. A. Larson, John M. Ryskamp, Robert A. Anderl, B. L. Broadhead, W. E. Ford III, J. L. Lucius, J. H. Marable, J. J. Wagschal, Karl Hornyik, Joseph A. Naser, D. Gauthier, C. Caput, F. Bourdeau, George C. Fullmer, Robert E. Einziger, Sharon D. Atkin, David E. Stellrecht, V. Pasupathi, Peter Weimar, Wolfgang Ernst, O. Götzmann, C. E. Johnson, S. W. Tam, P. E. Blackburn, D. C. Fee, R. L. Klueh, J. T. Dawson, G. Smith, T. F. Bott)
Materials Performance in CANDU Nuclear Steam Generators(G. F. Taylor, D. P. Dautovich)

EROS: An Experimental Breeder Reactor II Operational Safety Code

E. M. Dean, H. A. Larson

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 7-19

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A16182

Sensitivity and Uncertainty Analysis of the Coupled Fast Reactivity Measurements Facility Central Flux Spectrum

John M. Ryskamp, Robert A. Anderl, B. L. Broadhead, W. E. Ford III, J. L. Lucius, J. H. Marable, J. J. Wagschal

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 20-35

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A16183

RETRAN Analysis of the Turbine Trip Tests Performed at the Peach Bottom Atomic Power Station Unit 2

Karl Hornyik, Joseph A. Naser

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 36-49

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A16184

Environmental Gamma-Ray Measurement Methods for French Nuclear Installation Impact Studies

D. Gauthier, C. Caput, F. Bourdeau

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 50-57

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A16185

Boiling Water Reactor Cycle Extension Operation

George C. Fullmer

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 58-64

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT82-A16186

High Temperature Postirradiation Materials Performance of Spent Pressurized Water Reactor Fuel Rods Under Dry Storage Conditions

Robert E. Einziger, Sharon D. Atkin, David E. Stellrecht, V. Pasupathi

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 65-80

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16187

Mol-7B—An 18-Pin Bundle Operating 200 Days Beyond Breach

Peter Weimar, Wolfgang Ernst

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 81-89

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16188

Combination of Fuel-Cladding Chemical and Mechanical Interactions in Mixed Oxide Fuel Pins

O. Götzmann

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 90-103

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16189

Fuel Chemistry Impact on Vented Fuel Pin Design

C. E. Johnson, S. W. Tam, P. E. Blackburn, D. C. Fee

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 104-113

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16190

Heat Treatment of Cr—1 Mo Steel for Breeder Reactor Steam Generators

R. L. Klueh

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 114-124

Technical Paper / Material / dx.doi.org/10.13182/NT82-A16191

Measurement of Thermal Power Density Distributions by Fuel Pin Gamma Scanning

J. T. Dawson, G. Smith

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 125-133

Technical Paper / Technique / dx.doi.org/10.13182/NT82-A16192

An Assessment of TRAC-PD2 Refill Calculations Based on Creare Countercurrent Flow Tests

T. F. Bott

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 134-139

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT82-A16193

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use