First overpower tests of metallic IFR [Integral Fast Reactor] fuel in TREAT [Transient Reactor Test Facility] Data and analysis from tests M5, M6, and M7.

First overpower tests of metallic IFR [Integral Fast Reactor] fuel in TREAT [Transient Reactor Test Facility] [electronic resource] : Data and analysis from tests M5, M6, and M7.

Results and analyses of margin to cladding failure and pre-failure axial expansion of metallic fuel are reported for TREAT in-pile transient overpower tests M5--M7. These are the first such tests on reference binary and ternary alloy fuel of the Integral Fast Reactor (IFR) concept with burnup rangin...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1989.
Subjects:
Treat Reactor.
Fuel Elements.
Ifr Reactor.
Performance Testing.
Transients.
Reactor Cores.
Reactor Safety.
Burnup.
Failure Mode Analysis.
Melting.
Flow Rate.
Reactor Instrumentation.
Reactor Cooling Systems.
Hydraulics.
Heat Transfer.
Calibration.
Experimental Data.
Measuring Methods.
Fission Products.
Pressure Effects.
Fuel Cans.
Specific Nuclear Reactors And Associated Plants.
General Studies Of Nuclear Reactors.

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Call Number: E 1.99:anl-ifr--124
E 1.99:anl-ifr--124 Available

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