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Volume 8

Number 6

Increasing Maximum Enrichment Processing Capability Through Criticality Calculations

D. L. Dunaway, G. P. Miller, W. A. Johnson

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 482-487

Fuel Cycle / dx.doi.org/10.13182/NT70-A28647

Gas Pulse Impregnation of Graphite with Carbon

R. L. Beatty, D. V. Kiplinger

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 488-495

Fuel / dx.doi.org/10.13182/NT70-A28648

Plutonium Recycling in Heavy-Water-Moderated Thorium Reactor Systems

J. Darvas, U. Hansen, E. Teuchert

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 496-506

Fuel / dx.doi.org/10.13182/NT70-A28649

Compatibility of (U,Th)O2 with Graphite During Irradiation

J. A. Conlin, D. R. Cuneo, E. L. Long, Jr., C. L. Segasser

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 507-515

Material / dx.doi.org/10.13182/NT70-A28650

The Rapid Acquisition and Analysis of Gamma-Spectrometer Data Using a Small Computer

N. I.Sax, J. C. Daly

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 516-521

Instrument / dx.doi.org/10.13182/NT70-A28651

Use of a Pulse Detector for Reactor Noise Measurements

J. R. Trinko, Jr., S. H. Hanauer

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 522-530

Technique / dx.doi.org/10.13182/NT70-A28652

Neutron Source-Strength Determination by Student Laboratories

B. W. McGhee, W. W. Graham, III, M. R. Haroon

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 531-535

Education / dx.doi.org/10.13182/NT70-A28653

Fabrication of a 238Pu Heat Source for a Cardiac Pacemaker

D. L. Fleming, C. O. Brewer, D. L. Coffey

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 536-538

Radioisotope / dx.doi.org/10.13182/NT70-A28654