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.

FASTER Test Reactor Preconceptual Design

Jun 26, 2017, 4:50 PM
20m
Room 1 (Yekaterinburg)

Room 1

Yekaterinburg

ORAL Track 1. Innovative Fast Reactor Designs 1.2 SFR DESIGN & DEVELOPMENT - 2

Speaker

Mr Christopher Grandy (Argonne National Laboratory)

Description

The FASTER test reactor was designed as part of the U.S. Advanced Demonstration and Test Reactor Options (ADTR) Study in 2015/2016. The ADTR study provided an assessment of advanced reactor technology options and is intended to provide a sound comparative technical context for future decisions concerning these technologies. Point designs for a select number of concepts were commissioned. One of the two test reactor point designs was a sodium-cooled fast test reactor called FASTER. FASTER is a sodium-cooled, metal alloy fueled fast reactor with a core thermal power rating of 300MW. The FASTER plant was designed with extended testing capabilities in mind while trying to keep the reactor plant as simple as possible. The main function of the FASTER plant is to provide high neutron flux irradiation capability for both fast neutron spectrum and thermal neutron spectrum applications. The FASTER reactor plant incorporates an innovative core arrangement that also provides for irradiation testing in closed loops with different working fluids. This paper will describe the design characteristics of the FASTER plant and provide background information on the ADTR study and its objectives.

Country/Int. Organization

United States of America

Primary author

Mr Christopher Grandy (Argonne National Laboratory)

Presentation materials