American Nuclear Society

/Create an Account

Home

Home / Publications / Journals / Nuclear Technology / Volume 37 / Number 3

Volume 37

Number 3

Table of Contents
Authors(G. M. Borgonovi, R. H. Brogli, Claus Elter, Eberhard, Haug Helmut, Morassi, Darrell F., Newman Bryan, F. Gore, Hsiang-Shou Cheng, David J. Diamond, Ming-Shih Lu, Mario D. Carelli, R. T. Santoro, V. C. Baker, J. M. Barnes, Koichi Sekimizu, Andre Renoux, Jean Yves Barzic, Guy J. Madelaine, Pierre Zettwoog, J. E. Till, E. S. Bomar, L. E. Morse, V. J. Tennery, G. Oliva, G. Palmiotti, M. Salvatores, L. Tondinelli, N. L Baldwin, P. Winchell, S. Langer)
A Conceptual Reprocessing and Waste Management Scheme for Zircaloy-Clad Thoria Fuels(H. S. Levine, R. L. Schwoebel)
Recommendations for the Calculation of Materials Irradiation Exposure(V. Chernyshev, Scientific Secretary)
Comments on “Recent Developments in the Design of Conceptual Fusion Reactors”(M. Levenson)
Reply to“Comments on ‘Recent Developments in the Design of Conceptual Fusion Reactors’”(F. L. Ribe)

Resource Utilization of Symbiotic High-Temperature Gas-Cooled Reactor Systems

G. M. Borgonovi, R. H. Brogli

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 196-203

Technical paper / Reactor / dx.doi.org/10.13182/NT78-A31990

Effects of A Pipe Rupture Accident on the Reactor Internals in a Boiling Water Reactor Demonstrated by the Example of Philippsburg 1

Claus Elter, Eberhard Haug, Helmut Morassi

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 204-226

Technical paper / Reactor / dx.doi.org/10.13182/NT78-A31991

Neutron Multiplication Factors as a Function of Temperature: A Comparison of Calculated and Measured Values for Lattices Using ²³³U0₂-Th0₂ Fuel in Graphite

Darrell F. Newman, Bryan F. Gore

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 227-245

Technical paper / Reactor / dx.doi.org/10.13182/NT78-A31992

Boiling Water Reactor Scram Reactivity Characteristics

Hsiang-Shou Cheng, David J. Diamond, Ming-Shih Lu

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 246-260

Technical paper / Reactor / dx.doi.org/10.13182/NT78-A31993

Core Exit Instrumentation of the Clinch River Breeder Reactor Plant

Mario D. Carelli

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 261-273

Technical paper / Reactor / dx.doi.org/10.13182/NT78-A31994

NeutronIcs and Photonics Calculations for the Tokamak Experimental Power Reactor

R. T. Santoro, V. C. Baker, J. M. Barnes

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 274-295

Technical paper / Reactor / dx.doi.org/10.13182/NT78-A31995

A Hierarchy Level Scheme for Quasi-Optimum Fuel Assembly Loading in Boiling Water Reactors

Koichi Sekimizu

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 296-312

Technical paper / Fuel Cycle / dx.doi.org/10.13182/NT78-A31996

Quelques Caracteristiques De L’Air D’Une Mine D’Uranium

André Renoux, Jean Yves Barzic, Guy J. Madelaine, Pierre Zettwoog

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 313-327

Technical paper / Chemical Processing / dx.doi.org/10.13182/NT78-A31997

A Radiological Assessment of Reprocessing Advanced Liquid-Metal Fast Breeder Reactor Fuels

J. E. Till, E. S. Bomar, L. E. Morse, V. J. Tennery

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 328-339

Technical paper / Fuel / dx.doi.org/10.13182/NT78-A31998

Elimination of Transuranium Elements by Burnup in a Power Fast Breeder Reactor

G. Oliva, G. Palmiotti, M. Salvatores, L. Tondinelli

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 340-352

Technical paper / Fuel / dx.doi.org/10.13182/NT78-A31999

Diffusion of Plutonium in High-Temperature Isotropic Pyrolytic Carbon

N. L. Baldwin, P. Winchell, S. Langer

Nuclear Technology / Volume 37 / Number 3 / March 1978 / Pages 353-357

Technical paper / Fuel / dx.doi.org/10.13182/NT78-A32000

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use