Published 2017 | Version v1
Journal article

The characterization of microstructure and chemistry of transmutation fuels

  • 1. Department of Materials Science and Engineering, University of Florida, Gainesville, FL, 32611 (United States)
  • 2. Idaho National Laboratory, PO Box 1625 MS 6188, Idaho Falls, ID 83415 (United States)

Description

The goal of the fast reactor development programs is fabrication and certification of a nuclear fuel system that performs all functions of a conventional fuel while destroying recycled actinides. Metal fuels, such as U-Pu-Zr fuels, are considered to be candidates for this application. The physical and mechanical properties, as well as behavior laws and correlations of metal alloy fuel, all of which define the behavior and performance of metal alloy fuels has been investigated in detail. The results indicated that the prospect for fueling a future fast spectrum reactor using metal fuels is excellent. There are several challenges associated with the fuel implementation in reactor environment. One of the limiting factors in lifetime and safety of thermal and fast reactor systems is fuel swelling and resulting fission product transport to cladding. Understanding diffusion kinetics and phases formed between metal fuel and cladding upon exposure to high temperatures typical in reactor environment is critical for ensuring integrity, safety, and performance of the material, advancement of this type of fuel in the future, and securing long-term success of the nuclear fleet. The first step to understanding fuel-cladding interaction is investigation of an as-cast fuel microstructure. Despite the importance of these fuels, detailed description of microstructures in these materials is extremely limited. The majority of published results are based on characterization of as-cast microstructures of these fuels in scanning electron microscopes (SEM). In this work, we present the results from microstructural characterization of metallic Pu-based fuels, which is essential in the validation of current and future atomistic and meso-scale modeling efforts. A firm understanding of microstructural evolution in reactor materials is imperative and will lead to deeper understanding of in-reactor degradation behavior, creating a new generation of radiation-resistant materials and fuels with the potential for significant increases in burn-up

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
116
Journal Page Range
p. 352-353
ISSN
0003-018X

Conference

Title
2017 Annual Meeting of the American Nuclear Society
Dates
11-15 Jun 2017
Place
San Francisco, CA (United States)

Optional Information

Notes
3 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)