In-Reactor Creep Rupture Experiment in the Materials Open Test Assembly (MOTA)

Raymond Puigh; Robert Schenter

doi:10.1520/STP87019850018

SYMPOSIA PAPER Published: 09 February 2018

STP87019850018

In-Reactor Creep Rupture Experiment in the Materials Open Test Assembly (MOTA)

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The capabilities of the Materials Open Test Assembly (MOTA) irradiation vehicle and the Fast Flux Test Facility (FFTF) cover gas monitoring system are described in relation to the creep rupture experiment during FFTF Cycle 2 operation. The creep rupture specimen matrix in MOTA includes both U. S. and foreign alloys at irradiation temperatures of 575, 605, 670, and 750°C. For exposure times less than 2400 h and fluences less than 3.2 × 10²² neutrons (n)/cm² (E > 0.1 MeV), neutron irradiation does not impact the rupture times for the U. S. alloys irradiated in MOTA.

Author Information

Puigh, Raymond, J.

Westinghouse Hanford Company, Richland, WA, US

Schenter, Robert, E.

Westinghouse Hanford Company, Richland, WA, US

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Details

Developed by Committee: E10

Pages: 795–802

DOI: 10.1520/STP87019850018

ISBN-EB: 978-0-8031-7679-9

ISBN-13: 978-0-8031-0592-8

In-Reactor Creep Rupture Experiment in the Materials Open Test Assembly (MOTA)

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