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Volume 34

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Number 1

Table of Contents
Authors(László Maróti, S. Garribba, A. Ovi, Ora R. Citron, Kurt-Jürgen Vogt, S. Banerjee, S. R. Hatcher, A. D. Lane, H. Tamm, J. I. Veeder, Heinz E. Haefner, D. Haas, J. Van de Velde, M. Gaube, J. Ketels, C. Van Loon, D. A. Lee, D.A. Constanzo, D. P. Stinton, J. A. Carpenter, Jr., W. T. Rainey Jr., D. C. Canada, J. A. Carter, H. Venker, M. Bober, G. Schumacher, D. T. Raske, C. F. Cheng, W. O. Greenhalgh, D. T. Ott, G. Magnusson, I. Bergqvist)
Comment on Shielding Methods for the Design of Plutonium Processing Facilities(Eugene Normand)
Reply to “Comment on Shielding Methods for the Design Of Plutonium Processing Facilities”(Thomas C. Gillett)
Power Reactors in Member States, 1975 Edition
International Treaties Relating to Nuclear Control and Disarmament
Annual Review of Nuclear Science, Vols. 25 and 26
Reactor Core Fuel Management(Alexander Sesonske)
Environmental Aspects of Nuclear Power(Milton E. McLain, Jr.)

Axial Distribution of Void Fraction in Subcooled Boiling

László Maróti

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 8-17

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31825

Statistical Utility Theory for Comparison of Nuclear Versus Fossil Power Plant Alternatives

S. Garribba, A. Ovi

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 18-37

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31826

Institutional and Environmental Aspects of Geothermal Energy Development

Ora R. Citron

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 38-42

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT77-A31827

Empirical Investigations of the Diffusion of Waste Air Plumes in the Atmosphere

Kurt-Jürgen Vogt

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 43-57

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT77-A31828

Some Aspects of the Thorium Fuel Cycle in Heavy-Water-Moderated Pressure Tube Reactors

S. Banerjee, S. R. Hatcher, A. D. Lane, H. Tamm, J. I. Veeder

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 58-68

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT77-A31829

High-Pressure Capsule for the Irradiation of Fuel Swelling Specimens in the FR2 Reactor

Heinz E. Haefner

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 69-74

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31830

Results of the Postirradiation Examinations of the Rapsodie-I Experiment Fuel Pins

D. Haas, J. Van de Velde, M. Gaube, J. Ketels, C. Van Loon

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 75-88

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31831

In-Line Monitoring of Effluents from High-Temperature Gas-Cooled Reactor Fuel Particle Preparation Processes by Mass Spectrometry

D. A. Lee, D. A. Constanzo, D. P. Stinton, J. A. Carpenter, Jr., W. T. Rainey, Jr., D. C. Canada, J. A. Carter

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 89-97

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31832

Influence of the Radial Temperature Gradient on Cladding Dilatation

H. Venker, M. Bober, G. Schumacher

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 98-100

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31833

Fatigue Crack Propagation in Types 304 and 308 Stainless Steel at Elevated Temperatures

D. T. Raske, C. F. Cheng

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 101-110

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31834

A Reusable Frame Greenhouse That Saves Money and Erection Time and Reduces Waste Generation

W. O. Greenhalgh, D. T. Ott

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 111-113

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT77-A31835

14.7-MeV Neutron Capture Cross-Section Measurements with Improved Activation Technique

G. Magnusson, I. Bergqvist

Nuclear Technology / Volume 34 / Number 1 / June 1977 / Pages 114-121

Technical Paper / Technique / dx.doi.org/10.13182/NT77-A31836

Number 2

Table of Contents
Table of Contents
Authors(V. Marinelli, José Porto, F. L. Ribe, Timothy C. Kessler, Gary B. Fader, R. A. Krakowski, R. L. Hagenson, G. E. Cort, B. L. Koponen, W. J. Penn, R. K. Lo, J. C. Wood, T. Serpekian, R. Hecker, Hans U. Borgstedt, Günther Frees, Helga Schneider, George R. Fegan, Leo E. Chulos)
A New Approach to Assessing Fusion Plasma-Materials Interactions(F. Cafasso, D. Gruen, M. Kaminsky, J. E. Robinson, H. Wiedersich)
Prediction of Fission Gas Retained in Mixed-Oxide Fuels(H. Zimmermann)

Critical Heat Flux: A Review of Recent Publications

V. Marinelli

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 135-171

Technical Paper / Critical Review / dx.doi.org/10.13182/NT77-A39695

Generator of Reactivity Functions

Jose Porto

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 172-178

dx.doi.org/10.13182/NT77-A38428

Generator of Reactivity Functions

José Porto

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 172-178

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A39696

Recent Developments in the Design of Conceptual Fusion Reactors

F. L. Ribe

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 179-208

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A39697

A Best-Judgment Analysis of Emergency Core Cooling System Performance

Timothy C. Kessler, Gary B. Fader

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 209-216

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A39698

First Wall Thermal-Mechanical Analyses of the Reference Theta-Pinch Reactor

R. A. Krakowski, R. L. Hagenson, G. E. Cort

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 217-241

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A39699

Reactivity Enhancement in Transportation and Storage Arrays Due to Fissile Material Density Reductions

B. L. Koponen

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 242-248

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A39700

CANDU Fuel-Power Ramp Performance Criteria

W. J. PENN, R. K. LO, J. C. WOOD

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 249-268

dx.doi.org/10.13182/NT77-A38430

CANDU Fuel—Power Ramp Performance Criteria

W. J. Penn, R. K. Lo, J. C. Wood

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 249-268

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A39701

Investigation of High-Temperature Reactor Heat Exchanger Materials

T. Serpekian, R. Hecker

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 269-289

Technical Paper / Material / dx.doi.org/10.13182/NT77-A39702

Corrosion and Creep of Pressurized Stainless-Steel Tubes in Liquid Sodium at 873 and 973 K

Hans U. Borgstedt, Günther Frees, Helga Schneider

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 290-298

Technical Paper / Material / dx.doi.org/10.13182/NT77-A39703

Transition Matrix Approach to the Solution of the Bateman Equations

George R. Fegan

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 299-305

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT77-A39704

An Improved Method for Operating Sodium System Cold Traps

Leo E. Chulos

Nuclear Technology / Volume 34 / Number 2 / July 1977 / Pages 306-307

Technical Note / Reactor / dx.doi.org/10.13182/NT77-A39705

Number 3

Table of Contents
Authors(E. L. Simmons, Donald J. Dudziak, S. A. W. Gerstl, R. R. Fullwood, R. C. Erdmann, E. T. Rumble, G. S. Lellouche, Petros T. Antonopoulos, Joe C. Turnage, E. T. Cheng, T. Y. Sung, D. K. Sze, Johannes Wolters, Manfred Nickel, R. G. Alsmiller, Jr., J. Barish, C. R. Weisbin, Friedrich Niehaus, Harry J. Otway, Jose M. Aragonés, José M. Martínez-Val, María R. Corella, Ned E. Bibler, O. K. Tallent, J. C. Mailen, B.-G. Brodda, D. Heinen, D. Cordall, R. M. Cornell, K. W. Jones, J. S. Waddington, Roger Bonniaud)
Comments on “Economic Alternatives for the Long-Term Use of Plutonium Produced in Light Water Reactors”(Henry C. Ott)
Reply to “Comments on ‘Economic Alternatives for the Long-Term Use of Plutonium Produced in Light Water Reactors’”(K. Hnilica)
A Short-Duration Leach Test for Radioactive Waste Forms(A. W. Lynch)
A Guide to Radiation Protection
Radiation Protection by Shielding
The Nuclear Air Cleaning Handbook
World Survey of Major Facilities in Controlled Fusion Research
Annual Review of Energy, Volume 1
Annual Review of Materials Science, Volume 6
Advances in Nuclear Science and Technology, Volume 9
Methods in Computational Physics, Volume 15
Methods in Computational Physics, Volume 16

Nuclear Design Sensitivity Analysis for a Fusion Reactor

E. L. Simmons, Donald J. Dudziak, S. A. W. Gerstl

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 317-340

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31797

Application of the Bayes Equation to Predicting Reactor System Reliability

R. R. Fullwood, R. C. Erdmann, E. T. Rumble, G. S. Lellouche

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 341-346

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31798

Management Analysis of Nuclear Allocation for the Generation of Electricity

Petros T. Antonopoulos, Joe C. Turnage

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 347-361

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31799

Neutronics Studies of the Gas-Carried Lithium Oxide Cooling-Breeding Fusion Reactor Blanket and Shield

E. T. Cheng, T. Y. Sung, D. K. Sze

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 362-368

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31800

Elimination of Flow-Rate Fluctuations in the Core of the FRJ-2 Research Reactor and Its Usefulness for Reactor Operation

Johannes Wolters, Manfred Nickel

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 369-375

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31801

Uncertainties in Calculated Heating and Radiation Damage in the Toroidal Field Coil of a Tokamak Experimental Power Reactor Due to Neutron Cross-Section Errors

R. G. Alsmiller, Jr., J. Barish, C. R. Weisbin

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 376-386

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31802

The Cost Effectiveness of Remote Nuclear Reactor Siting

Friedrich Niehaus, Harry J. Otway

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 387-397

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT77-A31803

Core-State Models for Fuel Management of Equilibrium and Transition Cycles in Pressurized Water Reactors

José M. Aragonés, José M. Martínezval, María R. Corella

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 398-411

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT77-A31804

Radiolytic Instability of Ferrous Sulfamate in Nuclear Process Solutions

Ned E. Bibler

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 412-415

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31805

Effects of Metal lon Impurities on PuO₂ Dissolution in Nitric-Hydrofluoric Acid Solution

O. K. Tallent, J. C. Mailen

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 416-419

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31806

Solvent Performance in THTR Nuclear Fuel Reprocessing. Part I: Calculation of Doses Received by TBP-n-Paraffin Extractant in Reprocessing THTR Fuels Applying a THOREX Flowsheet

B.-G. Brodda, D. Heinen

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 420-427

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31807

Solvent Performance in THTR Nuclear Fuel Reprocessing. Part II: On the Formation of Dibutyl Phosphoric Acid by Radiolytic and Hydrolytic Degradation of the TBP-n-Paraffin Extractant

B.-G. Brodda, D. Heinen

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 428-437

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31808

Fuel Failures in the Dodewaard Boiling Water Reactor

D. Cordall, R. M. Cornell, K. W. Jones, J. S. Waddington

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 438-448

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31809

La Vitrification en France des Solutions de Produits de Fission

Roger Bonniaud

Nuclear Technology / Volume 34 / Number 3 / August 1977 / Pages 449-460

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT77-A31810