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Volume 47

Number 2

Table of Contents
Authors(V. C. Badham, W. E. Kastenberg, G. C. Pomraning, D. Okrent, W. W. Weaver, Juan J. Carbajo, Paul A. Howard, K. J. Longua, G. K. Whitham, C. C. Allen, Mitsugu Tanaka, R. D. Gasser, W. T. Pratt, F. H. Welch, O. P. Steele III, Jörg Hadermann, T. A. Parish, J. W. Davidson, Howard Ocken, W. E. Tadlock, G. C. Abell, R. H. Steinmeyer, E. J. Allen, S. R. McNeany)
Neutron Transmutation Doping in Semiconductors(K. Heydorn)

Accidental Criticality of a Fusion-Fission Hybrid Blanket Design

V. C. Badham, W. E. Kastenberg, G. C. Pomraning, D. Okrent

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 221-233

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32428

Deterministic Criteria Versus Probabilistic Analyses: Examining the Single Failure and Separation Criteria

W. W. Weaver

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 234-243

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32429

PLENUM-2A, A Program for Transient Analysis of Liquid-Metal Fast Breeder Reactor Outlet Plenums

Juan J. Carbajo, Paul A. Howard

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 244-265

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32430

Ultrasonic Inspection of Liquid-Metal Fast Breeder Reactor Steam Generator Duplex Tubing

K. J. Longua, G. K. Whitham, C. C. Allen

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 257-267

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32431

Heat Transfer of a Spray Droplet in a Nuclear Reactor Containment

Mitsugu Tanaka

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 268-281

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32432

Containment Response to Postulated Core Meltdown Accidents in the Fast Flux Test Facility

R. D. Gasser, W. T. Pratt

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 282-307

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32433

Evaporative Removal of Sodium from Reactor Components

F. H. Welch, O. P. Steele III

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 308-311

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32434

Radionuclide Transport Through Heterogeneous Media

Jörg Hadermann

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 312-323

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT80-A32435

Reduction in the Toxicity of Fission Product Wastes Through Transmutation with Deuterium-Tritium Fusion Neutrons

T. A. Parish, J. W. Davidson

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 324-342

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT80-A32436

An Improved Evaluation Model for Zircaloy Oxidation

Howard Ocken

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 343-357

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32437

Gas Generation by Self-Radiolysis of Tritiated Waste Materials

W. E. Tadlock, G. C. Abell, R. H. Steinmeyer

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 358-362

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32438

Nondestructive Fissile Isotopic Measurement Technique for Uranium-233–Uranium-235 Fuels Using Prompt and Delayed Fission Neutron Counting

E. J. Allen, S. R. McNeany

Nuclear Technology / Volume 47 / Number 2 / February 1980 / Pages 363-377

Technical Paper / Analysis / dx.doi.org/10.13182/NT80-A32439

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