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Volume 44

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Number 1

Table of Contents
Authors(J. A. Vitti, L. D. Felten, N. G. Galluzzo, J. M. Otter, J. C. Brittingham, Michael J. Lineberry, Harold F. McFarlane, Peter J. Collins, Stuart G. Carpenter, W. P. Barthold, J. C. Beitel, Y. H. Bouget, M. Cosimi, P. Hammer, G. Humbert, F. Lyon, M. Martini, H. S. Bailey, Y. S. Lu, P. Beslu, G. Frejaville, P. Jeanson, Philip M. Garrett, Robert A. Shaw, Fumio Murata, Kanji Kato, Fumio Tomizawa, Isao Sumida, S. R. MacEwen, A. R. Causey, Elizabeth Peelle, S. R. Bierman, B. M. Durst, E. D. Clayton, R. I. Scherpelz, Howard T. Kerr, Nicholas Tsoulfanidis, M. Hossein Jankhah, M. M. Hall, Jr., B. Wei-Teh Lee, S. H. Levine, W. A. Jester, F. E. LeVert, R. D. Mosteller, Warren M. Andrews, Odelli Ozer, W. J. Eich)
Preface: Nonconventional Core Designs of Liquid-Metal Fast Breeder Reactors(Charles Till)

Nuclear Design and Economic Comparison of a Conventional and Bullseye Liquid-Metal Fast Breeder Reactor Core

J. A. Vitti, L. D. Felten, N. G. Galluzzo, J. M. Otter, J. C. Brittingham

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 10-20

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32235

Physics Studies of a Heterogeneous Liquid-Metal Fast Breeder Reactor

Michael J. Lineberry, Harold F. McFarlane, Peter J. Collins, Stuart G. Carpenter

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 21-43

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32236

Performance Characteristics of Homogeneous Versus Heterogeneous Liquid-Metal Fast Breeder Reactors

W. P. Barthold, J. C. Beitel

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 44-60

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32237

Physics Performances of a Heterogeneous Fast Reactor Core Concept Studied in MASURCA

Y. H. Bouget, M. Cosimi, P. Hammer, G. Humbert, F. Lyon, M. Martini

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 61-75

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32238

Nuclear Performance of Liquid-Metal Fast Breeder Reactors Designed to Preclude Energetic Hypothetical Core Disruptive Accidents

H. S. Bailey, Y. S. Lu

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 76-82

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32239

Preface: Occupational Radiation Exposure at Nuclear Power Plants

E. A. Warman

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Page 83

Occupational Radiation Exposure at Nuclear Power Plants / dx.doi.org/10.13182/NT79-A32240

Occupational Radiation Exposure at French Power Plants: Measurement and Prediction

P. Beslu, G. Frejaville, P. Jeanson

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 84-90

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32241

Quantifying Plant Availability, ALARA, and Occupational Radiation Exposure Relationships

Philip M. Garrett

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 91-96

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32242

Getting at the Source: Reducing Radiation Fields

Robert A. Shaw

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 97-103

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32243

Development of a Diagnosis System for a Boiling Water Reactor

Fumio Murata, Kanji Kato, Fumio Tomizawa, Isao Sumida

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 104-117

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32244

Analysis of the Interaction of Fuel Channels with the End Shields in CANDU Reactors

S. R. MacEwen, A. R. Causey

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 118-131

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32245

Mitigating Community Impacts of Energy Development: Some Examples for Coal and Nuclear Generating Plants in the U.S.

Elizabeth Peelle

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 132-140

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT79-A32246

Critical Experiments with Fast Test Reactor Fuel Pins in Water

S. R. Bierman, B. M. Durst, E. D. Clayton, R. I. Scherpelz, Howard T. Kerr

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 141-151

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT79-A32247

Economic Performance of Liquid-Metal Fast Breeder Reactor and Gas-Cooled Fast Reactor Radial Blankets

Nicholas Tsoulfanidis, M. Hossein Jankhah*

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 152-171

Technical Paper / Economic / dx.doi.org/10.13182/NT79-A32248

Multiaxial Creep Equations for Nonlinear and Volume-Nonconservative In-Reactor Creep

M. M. Hall, Jr.

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 172-176

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32249

Study of an Optimum Design for Subcritical Neutron Multipliers Using Californium-252 Neutron Sources

B. Wei-Teh Lee, S. H. Levine, W. A. Jester

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 177-187

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT79-A32250

Application of the Self-Powered Detector Concept in the Design of a Threshold Gamma-Ray Detector

F. E. LeVert

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 188-191

Technical Paper / Instrument / dx.doi.org/10.13182/NT79-A32251

Plutonium Isotopic Calculations for a Modern Light Water Reactor

R. D. Mosteller*, Warren M. Andrews, Odelli Ozer, W. J. Eich

Nuclear Technology / Volume 44 / Number 1 / June 1979 / Pages 192-197

Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT79-A32252

Number 2

Table of Contents
Authors(Karol J. Mysels, Paul A. Howard, Juan J. Carbajo, A. L. Casadei, P. J. Turinsky, Stan Kaplan, B. John Garrick, Rodney R. Gay, Bo-In Lin, Burt Zolotar, Joel Weisman, A. J. Caputo, D. R. Johnson, C. K. Bayne, M. G. Seitz, P. G. Rickert, S. Fried, A. M. Friedman, M. J. Steindler, R. S. Ondrejcin, S. P. Rideout, J. A. Donovan, D. R. Olander, Jinchoon Kim)
Comments on “A Simple Relationship of Maximum Δk Due to Compaction of Unmoderated Fissile Materials” and the Use of the Trombay Criticality Formula for the Same(Anil Kumar, M. Srinivasan)
Reply to “Comments on ‘a Simple Relationship of Maximum Δk Due to Compaction of Unmoderated Fissile Materials’ and the use of the Trombay Criticality Formula for the Same”(Charles R. Marotta)

Transverse Flow in High-Temperature Gas-Cooled Reactor Graphite Elements

Karol J. Mysels

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 203-209

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32255

Experimental Study of Scram Transients in Generalized Liquid-Metal Fast Breeder Reactor Outlet Plenums

Paul A. Howard, Juan J. Carbajo

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 210-220

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32256

An Improved Water Density Feedback Model for Pressurized Water Reactors

A. L. Casadei, P. J. Turinsky

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 221-230

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32257

On the Use of a Bayesian Reasoning in Safety and Reliability Decisions—Three Examples

Stan Kaplan, B. John Garrick

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 231-245

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT79-A32258

EFLOD Code for Reflood Heat Transfer

Rodney R. Gay

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 246-257

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT79-A32259

An Automated Procedure for Selection of Optimal Refueling Policies for Light Water Reactors

Bo-In Lin, Burt Zolotar, Joel Weisman

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 258-275

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT79-A32260

Factors Affecting Defective Fraction of Biso-Coated High-Temperature Gas-Cooled Reactor Fuel Particles During In-Block Carbonization

A. J. Caputo, D. R. Johnson, C. K. Bayne

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 276-283

Technical Paper / Fuel / dx.doi.org/10.13182/NT79-A32261

Migratory Properties of Some Nuclear Waste Elements in Geologic Media

M. G. Seitz, P. G. Rickert, S. Fried, A. M. Friedman, M. J. Steindler

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 284-296

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT79-A32262

Control of Stress Corrosion Cracking in Storage Tanks Containing Radioactive Waste

R. S. Ondrejcin, S. P. Rideout, J. A. Donovan

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 297-306

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32263

Separative Performance Transients in a Gas Centrifuge

D. R. Olander

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 307-314

Technical Paper / Isotope Separation / dx.doi.org/10.13182/NT79-A32264

D-D Neutron and X-Ray Yields from High-Power Deuterium Beam Injectors

Jinchoon Kim

Nuclear Technology / Volume 44 / Number 2 / July 1979 / Pages 315-321

Technical Paper / Accelerator / dx.doi.org/10.13182/NT79-A32265

Number 3

Table of Contents
Authors(Halil I. Avci, Gerald L. Kulcinski, M. A. Hoffman, R. A. Bari, H. Ludewig, W. T. Pratt, Y. H. Sun, D. J. Bender, S. J. Hakim, P. B. Abramson, Philip E. MacDonald, James M. Broughton, Jay W. Spore, Kazys K. Almenas, Joseph M. Marchello, Hans H. Frick, J. R. Lindgren, P. W. Flynn, L. C. Foster, M. J. F. Notley)
Crystalline Ceramics from Defense High-Level Wastes(G. J. McCarthy)

The Effect of Liquid-Metal Protection Schemes in Inertial Confinement Fusion Reactors

Halil I. Avci, Gerald L. Kulcinski

Nuclear Technology / Volume 44 / Number 3 / August 1979 / Pages 333-345

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32270

Convective Helium Cooling of Grids in Continuously Operated Neutral Beam Injectors

M. A. Hoffman

Nuclear Technology / Volume 44 / Number 3 / August 1979 / Pages 346-356

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32271

Accident Progression for a Loss-of-Heat-Sink with Scram in a Liquid-Metal Fast Breeder Reactor

R. A. Bari, H. Ludewig, W. T. Pratt, Y. H. Sun

Nuclear Technology / Volume 44 / Number 3 / August 1979 / Pages 357-380

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32272