Nuclear Engineering, Volumes 4-9

Front Cover
The Institute, 1956 - Nuclear engineering

From inside the book

 

Contents

REACTORSITE SELECTION
1
THE FORD NUCLEAR REACTOR AND PHOENIX MEMORIAL LABORATORY
9
VENTILATING RADIOLOGICAL LABORATORIES
15
Copyright

29 other sections not shown

Other editions - View all

Nuclear Engineering, Volume 12

Snippet view - 1965
Nuclear Engineering, Volume 7

Snippet view - 1959
Nuclear Engineering, Part 23
American Institute of Chemical Engineers
Snippet view - 1972
View all »

Common terms and phrases

alloy aluminum aqueous assembly boiling calculated carbon cell channel chemical chlorine column concentration containing coolant cooling core corrosion cost cross section curve cycle density dissolver EBR-II effect efficiency enamels enriched Equation equipment experimental feed filter filtration fission products flow rate fluid fuel elements gamma heat transfer heat transfer coefficient helium high-temperature hood hot-channel factors hydrogen increase inlet irradiation laboratory lattice liquid material maximum measured ment metal method neutron flux nitric acid NUCLEAR ENGINEERING nuclear reactor obtained operation oxide phase plant plates plug plutonium pressure drop problem pump radiation radioactive range ratio reactant reaction removed rods sample shielding shown in Figure sintered slugs sodium solids solution solvent stainless steel steam storage sulfur dioxide surface SYMPOSIUM SERIES tank temperature thermal thermocouple tion triuranium octoxide tube uranium valve velocity waste zirconium

Bibliographic information

TitleNuclear Engineering, Volumes 4-9
Chemical engineering progress symposium series
ContributorAmerican Institute of Chemical Engineers
PublisherThe Institute, 1956
Original fromthe University of California
DigitizedJun 10, 2011
  
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