Metallic Fast Reactor Separate Effect Studies for Fuel Safety

Author:

Di Lemma Fidelma G.1,Jensen Colby B.2,Kane Joshua J.1,Chen Wei-Ying3,Liu Xiang1,Capriotti Luca1,Adkins Cynthia A.1,Kombaiah Boopathy1,Winston Alexander J.1,He Lingfeng1,Wachs Daniel4

Affiliation:

1. Characterization and Advanced PIE Division, Material Fuel Complex, Idaho National Laboratory, P. O. Box 1625 MS 6000, Idaho Falls, ID 83415-6000

2. Nuclear Fuels and Materials, Nuclear Science and Technology, Idaho National Laboratory, P. O. Box 1625 MS 3818, Idaho Falls, ID 83415-3818

3. Nuclear Science and Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Lemont, IL 60439

4. Nuclear Fuels and Materials, Nuclear Science and Technology, Idaho National Laboratory, P. O. Box 1625 MS 3690, Idaho Falls, ID 83415-3690

Abstract

Abstract Sodium-cooled Fast Reactors (SFR) are one of the advanced nuclear reactor concepts to be commercially applied for electricity production. The benefits of SFR are well-known and include: the possibility of a closed fuel cycle, proliferation resistance, nuclear waste minimization via actinides burning, and fissile breeding capabilities. Metallic fuel used in SFR has well demonstrated irradiation performance. However, more studies are necessary to optimize and extend operational and safety limits for their commercialization and licensing. This could be achieved through a better understanding of fuel behaviors during transient and of fuel failure thresholds. This paper describes the experimental Research and Development (R&D) program aimed at providing the necessary data to support the development of SFR-optimized safety limits. This program integrates separate effects testing and integral effects testing, combined with advanced Modeling and Simulation (M&S). This R&D program, finally, focuses on delivering the science-based information necessary for supporting the licensing and utilization of SFR based on metallic fuel. In this paper we will describe the three research areas centered on fuel development and focused on separate effect testing, namely: (1) microstructural, chemistry, and material properties; (2) thermo-mechanical behavior; and (3) source term and fission product behavior. Preliminary results from these Separate Effect Tests (SET) studies and the current instruments and experimental plan are also presented.

Funder

U.S. Department of Energy

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference34 articles.

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