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Volume 47

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

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