INVESTIGATION OF INNER AND OUTER RIBBED, TUBULAR GAS-COOLED FUEL ELEMENTS

Author: Presser, K. H.
Published: Germany : [publisher not identified], 1969.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1969.
Physical Description: microfiche : negative ; 11 x 15 cm
Additional Creators: Broeckerhoff, P. and Harth, R.

Availability

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Language Note

In German.

Report Numbers

JUL-618-RB

Other Subject(s)

Configuration
Finned tubes/heat transfer from, effects of fin configuration on optimum, (e/t).
Fins
Fuel cans
Fuel elements
Gas cooled reactors
Graphite moderated reactors
Heat transfer
N24300 - engineering-heat transfer & fluid flow
N38150 -power reactor development-fuels
Natural uranium fuel
Reactor fuel elements/cladding for natural uranium fueled gas cooled graphite moderated, effects of fin configuration on optimum heat transfer of tube shaped, (e/t).
Reactors, gas-cooled/fuel element cladding for natural uranium fueled graphite moderated, effects of fin configuration on optimum heat transfer of tube shaped, (e/t).
Reactors, graphite-moderated/fuel element cladding for natural uranium fueled gas cooled, effects of fin configuration on optimum heat transfer of tube shaped, (e/t).
Testing
Tubes

Collection

U.S. Atomic Energy Commission depository collection.

Note

NSA number: NSA-24-020568
OSTI Identifier 4168235
Research organization: Kernforschungsanlage, Juelich (West Germany). Institut fuer Reaktorbauelemente.

View MARC record | catkey: 47029104