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Volume 34

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

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