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DOE OSTI · 2352425

Conceptual Neutronics Scoping for Ramp Testing in the Advanced Test Reactor

Labossiere-Hickman, Travis J·Woolstenhulme, Nicolas E·Durtschi, Brian P·Kamerman, David W
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Abstract

With the closer of the Halden Boiling Water Reactor in 2018, the global capacity for in-reactor power ramp testing has been lost. As such tests provide valuable data for understanding pellet-cladding interaction (PCI) phenomena, finding new facilities for ramp testing is of interest to the United States Accident-Tolerant Fuel (ATF) Program. Several options at Idaho National Laboratory (INL) are being evaluated for adding ramp test capabilities. In the Transient Reactor Test Facility (TREAT), one option is testing inside a Transient Water Irradiation System in TREAT (TWIST) capsule. In the Advanced Test Reactor (ATR), one option under consideration is testing in an I-Loop toward the outer edge of the core. Another is testing in Loop-2A, located in the Center Flux Trap (CFT) of the ATR. In this paper, we examine the conceptual scoping for the Loop-2A experiment known as ATF-2Ramp.

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALSAccident Tolerant FuelIrradiation ExperimentsPCI Ramp Testing

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BibTeXRIS

Labossiere-Hickman, Travis J, Woolstenhulme, Nicolas E, Durtschi, Brian P, Kamerman, David W. 2023-11-15. Conceptual Neutronics Scoping for Ramp Testing in the Advanced Test Reactor. https://www.osti.gov/biblio/2352425

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