Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

Review of Transient Testing of Fast Reactor Fuels in the Transient REActor Test Facility (TREAT)

27 Jun 2017, 11:00
20m
Room 2 (Yekaterinburg)

Room 2

Yekaterinburg

ORAL Track 6. Test Reactors, Experiments and Modeling and Simulations 6.10 Other issues of code development and application

Speaker

Dr Colby Jensen (Idaho National Laboratory)

Description

The restart of the Transient REActor Test (TREAT) facility provides a unique opportunity to engage the fast reactor fuels community to reinitiate in-pile experimental safety studies. Historically, the TREAT facility played a critical role in characterizing the behavior of both metal and oxide fast reactor fuels under off-normal conditions, irradiating hundreds of fuel pins to support fast reactor fuel development programs. The resulting test data has provided validation for a multitude of fuel performance and severe accident analysis computer codes. This paper will provide a review of the historical database of TREAT experiments including experiment design, instrumentation, test objectives, and salient findings. Additionally, the paper will provide an introduction to the current and future experiment plans of the U.S. transient testing program at TREAT.

Country/Int. Organization

USA/Idaho National Laboratory (US DOE)

Primary author

Dr Colby Jensen (Idaho National Laboratory)

Co-authors

Dr Daniel Wachs (Idaho National Laboratory) Mr Nicolas Woolstenhulme (Idaho National Laboratory) Dr William Carmack (Idaho National Laboratory)

Presentation materials