Understanding Manufacturing Scale-Up of Plasma Sprayed Zr Barrier Coatings on U-10Mo Fuels
Creators
- 1. SIGMA Division, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)
- 2. Materials Science and Technology - MST-8, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)
Description
The United States government is committed to further strengthening nuclear security and nonproliferation in order to reduce the threat of terrorists acquiring nuclear material. To meet this important mission, the US Department of Energy/National Nuclear Security Agency's Office of Material Management and Minimization (M3) Reactor Conversion Program minimizes the use of highly enriched uranium (HEU) in civilian applications by working with governments and facilities around the world to convert research reactors to the use of non-weapons-usable low-enriched uranium (LEU) fuels. Each reactor converted not only eliminates the need for HEU at civilian sites, but also reduces the amount of HEU being manufactured, stored, and transported, where it is at its most vulnerable. In instances where suitable LEU fuels do not exist for particular reactors to convert, the M3 Reactor Conversion Program (CONVERT) contributes to the development of new LEU fuels. Currently, the M3 Reactor Conversion Program is committed to developing a high-density U-Mo LEU fuel that will be able to convert high performance research reactors while establishing an efficient and economic fabrication capability to make the fuel. To that end, Los Alamos National Laboratory (LANL) has been tasked with developing a method to affix a Zirconium fuel diffusion barrier via plasma spraying that will prevent a reaction between the U-Mo fuel and the aluminum cladding. This report discusses the transitions from development of the plasma spray deposition process to a scientific understanding of pseudo-production conditions and quantification of coating layer properties, characterization, reproducibility, etc. Understanding quality assurance and its applications to experiment work is non-trivial; statistical analysis of various measurement techniques not only improve quality, but will allow for scale up of manufacturing
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 520-522
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52087859
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; CLADDING; COATINGS; DENSITY; DIFFUSION BARRIERS; HIGHLY ENRICHED URANIUM; LANL; MINIMIZATION; NUCLEAR FUELS; NUCLEAR SECURITY; PERFORMANCE; PLASMA; QUALITY ASSURANCE; RESEARCH REACTORS; SPRAYS; ZIRCONIUM
- Descriptors DEC
- ACTINIDES; DEPOSITION; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; FUELS; ISOTOPE ENRICHED MATERIALS; MANAGEMENT; MATERIALS; METALS; NATIONAL ORGANIZATIONS; OPTIMIZATION; PHYSICAL PROPERTIES; QUALITY MANAGEMENT; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SECURITY; SURFACE COATING; TRANSITION ELEMENTS; URANIUM; US DOE; US ORGANIZATIONS
Optional Information
- Notes
- 7 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)