Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components

RA Moen; JC Tobin; KC Thomas

doi:10.1520/STP26640S

SYMPOSIA PAPER Published: 01 January 1970

STP26640S

Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components

Source

This paper describes the analytical procedures that have been developed at Battelle-Northwest Laboratory (BNWL) and Westinghouse Advanced Reactors Division (ARD) to determine neutron fluence limits for certain components of the Fast Flux Test Facility (FFTF), namely the core barrel, core support structure, and the reactor vessel.

Author Information

Moen, RA

Pacific Northwest Laboratory, Battelle Memorial Institute, Richland, Wash.

Tobin, JC

Pacific Northwest Laboratory, Battelle Memorial Institute, Richland, Wash.

Thomas, KC

Westinghouse Electric Corp., Madison, Pa.

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Details

Developed by Committee: E10

Pages: 409–418

DOI: 10.1520/STP26640S

ISBN-EB: 978-0-8031-4593-1

ISBN-13: 978-0-8031-0014-5

Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components

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