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Volume 20

Number 1 | Number 2 | Number 3

Number 1

A Model of the Dynamic Behavior of the Coaxial-Flow Gaseous-Core Nuclear Reactor

Kyle H. Turner, Jr., Joseph D. Clement

Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 5-14

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31329

On the Emission Coefficient of Uranium Plasmas

R. T. Schneider, H. D. Campbell, J. M. Mack

Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 15-26

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31330

Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel

J. L. Straalsund, C. K. Day

Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 27-34

Technical Paper / Materials / dx.doi.org/10.13182/NT73-2

Radiation Doses from Hypothetical Exposures to Rulison Gas

C. J. Barton, R. E. Moore, S. R. Hanna

Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 35-50

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT73-A31332

Effects of Gas Mixture, Electrode Spacing, Gas Pressure, and Applied Voltage on the Gamma Performance of Fission Counters

L. D. Philipp, N. C. Hoitink, W. G. Spear, M. R. Wood

Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 51-59

Technical Paper / Instrument / dx.doi.org/10.13182/NT73-A31333

Continuous Conversion of Uranium/Plutonium Nitrates to Oxides

N. Levitz, D. E. Grosvenor, S. Vogler, F. G. Teats, N. Quattropani

Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 60-63

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT73-A31334

Proton Dosimeter Design for Distributed Body Organs

G. S. Khandelwal, J. W. Wilson

Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 64-67

Technical Note / Instrument / dx.doi.org/10.13182/NT73-A31335

Number 2

Spectral Analysis of Sampled Nuclear Reactor Plant Data with Heterodyne Digital Filtering Techniques

H. Roggenbauer, W. Seifritz, T. Lindmo

Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 79-85

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31343

Determination of Optimum Fuel Loadings in Pressurized Water Reactors Using Dynamic Programming

Richard B. Stout, Alan H. Robinson

Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 86-102

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT73-A31344

UO2 Pellet-Stack Shortening in a Boiling Water Reactor

F. List, P. Knudsen

Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 103-108

Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31345

Use of Metallic Thorium for LWBRs and LWRs

G. B. Zorzoli

Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 109-113

Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31346

First Report on Apparatus to Simulate In-Reactor Transient Heating Conditions in Oxide Fuel Columns

B. J. Wrona, J. T. A. Roberts, E. Johanson, W. D. Tuohig

Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 114-123

Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31347

Californium-252 Assay System for FBR-Type Fuel Pins

H. O. Menlove, R. A. Forster, J. L. Parker, Darryl B. Smith

Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 124-133

Technical Paper / Analysis / dx.doi.org/10.13182/NT73-A31348

Effect of Minor Alloy Variations on the Thermal Densification of Austenitic Stainless Steels

J. F. Bates, M. M. Paxton, J. L. Straalsund

Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 134-135

Technical Note / Material / dx.doi.org/10.13182/NT73-A31349

Number 3

Nuclear Power Plant Heat Rejection in an Arid Climate

Frederic C. Scofield, Rocco A. Fazzolare

Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 140-148

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31353

Methods for Calculating Vapor and Fuel Transport to the Secondary Containment in an LMFBR Accident

M. F. Kennedy, A. B. Reynolds

Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 149-160

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31354

A Review of Fusion-Fission (Hybrid) Concepts

B. R. Leonard, Jr.,

Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 161-178

Technical Paper / Reactors / dx.doi.org/10.13182/NT73-1

Storage Capacity for Fissile Material as a Function of Facility Size

C. L. Schuske, S. J. Altschuler

Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 179-189

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT73-A31356

Oxygen Interactions Between Sodium and Uranium-Plutonium Oxide Fuel

D. L. Smith

Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 190-199

Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31357

A High-Capacity Annular Centrifugal Contactor

G. J. Bernstein, D. E. Grosvenor, J. F. Lenc, N. M. Levitz

Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 200-202

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT73-A31358