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Volume 47

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Number 1

Table of Contents
Authors(G. L. Hofman, Shu-Chien Yung, Norman P. Wilburn, Constantine P. Tzanos, S. R. Bierman, B. M. Durst, E. D. Clayton, Jerzy Kubowski, G. A. Pertmer, S. K. Loyalka, G. Bandyopadhyay, J. A. Buzzell, Yakov Ben-Haim, K. Vinjamuri, D. E. Owen, F. Parras, M. Bosser, D. Milan, G. Berthollon, Valentin Casal, Bernard Cohen, Philip A. Anderson, J. P. Foster, A. Boltax, Nobuo Sasamoto, Kiyoshi Takeuchi, R. A. Lillie, R. T. Santoro, G. U. Greger, K. Schügerl)
Nuclear Power and Radioactive Waste(Yutaka Kono)

Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel

G. L. Hofman

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 7-22

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32408

Effect of Intrasubassembly Incoherencies on the Fast Test Reactor Unprotected Transient Overpower Accident

Shu-Chien Yung, Norman P. Wilburn

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 23-38

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32409

Analysis of the Differences in Breeding Ratio and Fissile Inventory Between Heterogeneous and Homogeneous Liquid-Metal Fast Breeder Reactors

Constantine P. Tzanos

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 39-50

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32410

Criticality Experiments with Subcritical Clusters of Low Enriched UO₂ Rods in Water with Uranium or Lead Reflecting Walls

S. R. Bierman, B. M. Durst, E. D. Clayton

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 51-58

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32411

Development of a Dynamics Model for the Research Reactor Maria

Jerzy Kubowski

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 59-69

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32412

Gravitational Collision Efficiency of Post Hypothetical Core Disruptive Accident Liquid-Metal Fast Breeder Reactor Aerosols: Spherical Particles

G. A. Pertmer, S. K. Loyalka

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 70-90

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32413

The Role of Fission Gas and Fuel Melting in Fuel Response During Simulated Hypothetical Loss-of-Flow Transients

G. Bandyopadhyay, J. A. Buzzell

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 91-109

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32414

Design Against Weathering of Iodine Filters

Yakov Ben-Haim

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 110-118

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT80-A32415

Helium Fill Gas Absorption in Pressurized UO₂ Fuel Rods During Irradiation

K. Vinjamuri, D. E. Owen

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 119-124

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32416

Heat Transfer in Pressurized Water Reactor Components Most Often Subject to Thermal Shock

F. Parras, M. Bosser, D. Milan, G. Berthollon

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 125-152

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32417

Design of High-Performance Fuel Pin Simulators for Thermodynamic Experiments with Nuclear Fuel Elements

Valentin Casal

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 153-162

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32418

Ocean Dumping of High-Level Waste—An Acceptable Solution We Can “Guarantee”

Bernard Cohen

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 163-172

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT80-A32419

Laboratory Simulation of High-Level Liquid Waste Evaporation and Storage

Philip A. Anderson

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 173-180

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT80-A32420

Effects of Temperature Changes on the Swelling Behavior of 20% Cold-Worked AISI Type 316 Stainless Steel

J. P. Foster, A. Boltax

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 181-188

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32421

Analysis of ⁶⁰Co Gamma-Ray Transport Through Air by Discrete-Ordinates Transport Codes

Nobuo Sasamoto, Kiyoshi Takeuchi

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 189-199

Technical Paper / Shielding / dx.doi.org/10.13182/NT80-A32422

Radiation Transport in Earth for Neutron and Gamma-Ray Point Sources Above an Air-Ground Interface

R. A. Lillie, R. T. Santoro

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 200-207

Technical Paper / Shielding / dx.doi.org/10.13182/NT80-A32423

Determination of the Concentration of Solutes in Liquids by Means of the (n,α) and (n,γ) Reactions

G. U. Greger, K. Schügerl

Nuclear Technology / Volume 47 / Number 1 / January 1980 / Pages 208-212

Technical Paper / Analysis / dx.doi.org/10.13182/NT80-A32424

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

Number 3

Table of Contents
Authors(F. A. Means, R. S. Rodliffe, K. Harding, M. Z. Youssef, R. W. Conn, W. F. Vogelsang, F. Beranek, R. W. Conn, R. T. Santoro, R. A. Lillie, R. G. Aismiller, Jr., J. M. Barnes, Tsutomu Hoshino, F. M. Sider, R. A. Matzie, Edward T. Maas, Jr., John M. Longo, Mitchel E. Cunningham, Courtney R. Hann, Anthony R. Olsen, Chien-chang Lin, J. J. Younger, Rajiv Kohli, Akio Ohno, Shojiro Matsuura, Auguste Zurkinden, J. M. Barnes, B. L. Bishop, R. T. Santoro, T. A. Gabriel)

An Investigation of Particulate Corrosion Product Transients in the Primary Coolant of the Winfrith Steam Generating Heavy Water Reactor

F. A. Means, R. S. Rodliffe, K. Harding

Nuclear Technology / Volume 47 / Number 3 / March 1980 / Pages 385-396

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32392

Tritium and Fissile Fuel Exchange Between Hybrids, Fission Power Reactors, and Tritium Production Reactors

M. Z. Youssef, R. W. Conn, W. F. Vogelsang

Nuclear Technology / Volume 47 / Number 3 / March 1980 / Pages 397-405

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32393

Neutron Moderation in Inertial Confinement Fusion Pellets and Effects on Damage and Radioactive Inventory

F. Beranek, R. W. Conn

Nuclear Technology / Volume 47 / Number 3 / March 1980 / Pages 406-411

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32394