Home / Publications / Journals / Nuclear Technology / Volume 8 / Number 6
Increasing Maximum Enrichment Processing Capability Through Criticality Calculations
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
Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 488-495
Plutonium Recycling in Heavy-Water-Moderated Thorium Reactor Systems
Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 496-506
Compatibility of (U,Th)O2 with Graphite During Irradiation
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
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
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
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
Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 536-538
Radioisotope / dx.doi.org/10.13182/NT70-A28654