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Volume 18

Number 1

Table of Contents
Authors(M. J. Bell, Mojtaba Taherzadeh, W. W. Hudritsch, Brian F. Ives, Harry T. Cullinan, Jr., John Y. Yang, T. F. Craft, G. G. Eichholz, S. J. Altschuler, C. L. Schuske, J. M. Donhowe, D. L. Klarstrom, M. L. Sundquist, W. J. Weber, D. C. Cutforth)
Radioisotope Engineering(Benjamin M. Ma)

Calculated Radiation Properties of Spent Plutonium Fuels

M. J. Bell

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 5-14

Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A16102

The Analytically Determined Response of Silicon Detectors to a Polyenergetic Neutron Beam

Mojtaba Taherzadeh

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 15-24

Technical Paper / Instrument / dx.doi.org/10.13182/NT73-A16103

Determination of Neutron Flux and Neutron Fluence from the Signal Current of a Self-Powered Rhodium Detector

W. W. Hudritsch

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 25-28

Technical Paper / Instrument / dx.doi.org/10.13182/NT73-A16104

A Radioactive Fluid Bed Reactor System for the Beta-Initiated Side Chain Chlorination of Toluene

Brian F. Ives, Harry T. Cullinan, Jr., John Y. Yang

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 29-45

Technical Paper / Radiation / dx.doi.org/10.13182/NT73-A16105

Decoloration of Textile Dye Waste Solutions by Combined Irradiation and Chemical Oxidation

T. F. Craft, G. G. Eichholz

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 46-54

Technical Paper / Radiation / dx.doi.org/10.13182/NT73-A16106

A Study of Criticality Parameters Affecting the Handling and Storage of Fissile Metal

S. J. Altschuler, C. L. Schuske

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 55-62

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT73-A16107

Radiation Blistering in Niobium

J. M. Donhowe, D. L. Klarstrom, M. L. Sundquist, W. J. Weber

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 63-66

Technical Note / Material / dx.doi.org/10.13182/NT73-A16108

Dimensioning Reactor Fuel Specimens from Thermal-Neutron Radiographs

D. C. Cutforth

Nuclear Technology / Volume 18 / Number 1 / April 1973 / Pages 67-70

Technical Note / Technique / dx.doi.org/10.13182/NT73-A16109

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