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Number 1
Number 2

Number 3

Number 1

Table of Contents
Authors (L. K. Mansur, J. C. Robinson, F. Shahrokhi, R. C. Kryter, Roy R. Fray, G. Bandyopadhyay, Shunsuke Uchida, Motoaki Utamura, Hideo Yusa, Hideo Maki, C. E. Johnson, D. C. Fee, F. A. Nichols, J. J. Sienicki, P. B. Abramson)

Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory
L. K. Mansur
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 5-34
Technical Paper | Critical Review | doi.org/10.13182/NT78-2
Calculation of the Scale Factor for Inference of Pressurized Water Reactor Core Barrel Motion from Neutron Noise Spectral Density
J. C. Robinson, F. Shahrokhi, R. C. Kryter
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 35-46
Technical Paper | Reactor | doi.org/10.13182/NT78-A26697
Quantification of Core Barrel Motion Using an Analytically Derived Scale Factor and Statistical Reactor Noise Descriptors
J. C. Robinson, F. Shahrokhi, R. C. Kryter
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 47-51
Technical Paper | Reactor | doi.org/10.13182/NT78-A26698
Potential Radiological Consequences of a Multiple Steam Generator Tube Rupture
Roy R. Fray
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 52-61
Technical Paper | Reactor | doi.org/10.13182/NT78-A26699
Fuel and Fission Gas Response to Simulated Thermal Transients: Experimental Results and Correlation with Fission Gas Release and Swelling Model
G. Bandyopadhyay
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 62-78
Technical Paper | Fuel | doi.org/10.13182/NT78-A26700
Application of the Warm Water Injection Method to Improve the Efficiency of In-Core Wet Sipping for Leaker Detection
Shunsuke Uchida, Motoaki Utamura, Hideo Yusa, Hideo Maki
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 79-88
Technical Paper | Fuel | doi.org/10.13182/NT78-A26701
Oxygen Getters for Fast Reactor Fuel Pins
C. E. Johnson, D. C. Fee
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 89-97
Technical Paper | Material | doi.org/10.13182/NT78-A26702
How Does One Predict and Measure Radiation Damage?
F. A. Nichols
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 98-105
Technical Paper | Material | doi.org/10.13182/NT78-A26703
Effects of Recent Modeling Developments in Prompt Burst Hypothetical Core Disruptive Accident Calculations
J. J. Sienicki, P. B. Abramson
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 106-115
Technical Note | Reactor | doi.org/10.13182/NT78-A26704

Number 2

Rationale for Incorporating Inservice Inspection Requirements During Nuclear Power Plant Design/Fabrication
Gary J. Dau
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 122-128
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Education | doi.org/10.13182/NT78-A26708
Materials and Design Interaction in Advanced Reactors
J. Boulton
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 129-137
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Education | doi.org/10.13182/NT78-A26709
The Effect of Swelling and Creep on Liquid-Metal Fast Breeder Reactor Performance
W. P. Barthold, J. C. Beitel
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 138-148
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Material | doi.org/10.13182/NT78-A26710
On the Probability of Loss of dc Power Following ac Failure in a Nuclear Power Plant
J. Chun, G. E. Apostolakis
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 149-158
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Reactor | doi.org/10.13182/NT78-A26711
Operation of the Water-to-Sodium Leak Detection System at the Experimental Breeder Reactor II
Marilyn M. Osterhout
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 159-169
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Reactor | doi.org/10.13182/NT78-A26712
Calculation of Radiological Dose due to Release of Tritium Oxides from Controlled Thermonuclear Reactors
T. E. McKone, W. E. Kastenberg
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 170-184
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Reactor Siting | doi.org/10.13182/NT78-A26713
The Interactions of Hydrazine, Ferrous Sulfamate, Sodium Nitrite, and Nitric Acid in Nuclear Fuel Processing Solutions
Leonard W. Gray
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 185-193
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Chemical Processing | doi.org/10.13182/NT78-A26714
Neutron Irradiation Effects on Carbon and Graphite Cloths and Fibers
W. J. Gray
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 194-207
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Material | doi.org/10.13182/NT78-A26715
Injecting Irradiation Samples with a Uniform Concentration of Helium Using Curium-244
N. H. Packan, W. A. Coghlan
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 208-213
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Radiation | doi.org/10.13182/NT78-A26716
High-Level Radioactive Waste Incorporation into (Special) Cements
Della M. Roy, George R. Gouda
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 214-219
Technical Note | Tutorial Materials/Design Interaction in Nuclear System / Chemical Processing | doi.org/10.13182/NT78-A26717

Number 3

Table of Contents
Authors (Jörgen Christensen, Franz Wolfgang Mayer, George C. Geisler, J. A. Urbanski, W. F. Witzig, Richard N. Oehlberg, Harold H. Scott, Naomichi Kanegae, Koh Hashiguchi, Ichiro Ikemoto, Masao Hori, H. Albrecht, V. Matschoss, H. Wild, J. S. Philbin, S. A. Dupree, Theodore M. Besmann, Terrence B. Lindemer, G. W. McNair, K. L. Peddicord, V. C. Rogers, K. Lassmann, W. Berkhahn, W. Ehrfeld, G.Krieg, A. Mack, J. M. Barnes, R. T. Santoro, T. A. Gabriel)
High-Level Radioactive Waste Management (R. B. Goranson)
Nuclear Fusion (World Survey of Major Facilities in Controlled Fusion Research) (W. Morris Farr)