Published April 25, 2016 | Version v1
Report

U-10Mo/Zr Interface Modeling using a Microstructure-Based FEM Approach

  • 1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

Description

The U-10Mo in low enrichments (LEU) has been identified as the most promising alternative to the current highly enriched uranium (HEU) used in the United States' fleet of high performance research reactors (USHPRRs). The nominal configuration of the new LEU U-10Mo plate fuel comprises a U-10Mo fuel foil enriched to slightly less than 20% U-235 (0.08'' to 0.02'' thick), a thin Zr interlayer/diffusion barrier (25 m thick) and a relatively thick outer can of 6061 aluminum. Currently, the Zr interlayer is clad by hot roll bonding. Previous studies and observations revealed a thinning of the zirconium (Zr) layer during this fuel fabrication process, which is not desirable from the fuel performance perspective. Coarse UMo grains, dendritic structures, Mo concentration segregation, carbides, and porosity are present in the as-cast material and can lead to a nonuniform UMo/Zr interface. The purpose of the current work is to investigate the effects of these microstructural parameters on the Zr coating variation. A microstructure-based finite-element method model was used in this work, and a study on the effect of homogenization on the interface between U-10Mo and Zr was conducted. The model uses actual backscattered electron-scanning electron microscopy microstructures, Mo concentrations, and mechanical properties to predict the behavior of a representative volume element under compressive loading during the rolling process. The model successfully predicted the experimentally observed thinning of the Zr layer in the as-cast material. The model also uses results from a homogenization model as an input, and a study on the effect of different levels of homogenization on the interface indicated that homogenization helps decrease this thinning. This model can be considered a predictive tool representing a first step for model integration and an input into a larger fuel fabrication performance model.

Availability note (English)

Available from http://www.pnnl.gov/main/publications/external/technical_reports/PNNL-25365.pdf; PURL: http://www.osti.gov/servlets/purl/1339915/

Additional details

Publishing Information

Imprint Pagination
36 p.
Report number
PNNL--25365

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
48053022
Subject category
S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
BINARY ALLOY SYSTEMS; BONDING; CARBIDES; COATINGS; COMPRESSION; DENDRITES; FINITE ELEMENT METHOD; FOILS; FORECASTING; FUEL PLATES; INTERFACES; LAYERS; MECHANICAL PROPERTIES; MICROSTRUCTURE; MODERATELY ENRICHED URANIUM; MOLYBDENUM ALLOYS; PERFORMANCE; POROSITY; RESEARCH REACTORS; ROLLING; SCANNING ELECTRON MICROSCOPY; SEGREGATION; SIMULATION; STATIC LOADS; THICKNESS; URANIUM 235; URANIUM BASE ALLOYS; URANIUM-MOLYBDENUM FUELS; VARIATIONS; ZIRCONIUM
Descriptors DEC
ACTINIDE ALLOYS; ACTINIDE NUCLEI; ACTINIDES; ALLOY NUCLEAR FUELS; ALLOY SYSTEMS; ALLOYS; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; CARBON COMPOUNDS; CRYSTALS; DIMENSIONS; ELECTRON MICROSCOPY; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; EVEN-ODD NUCLEI; FABRICATION; FUEL ELEMENTS; FUELS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; JOINING; MATERIALS; MATERIALS WORKING; MATHEMATICAL SOLUTIONS; METALS; MICROSCOPY; MINUTES LIVING RADIOISOTOPES; NUCLEAR FUELS; NUCLEI; NUMERICAL SOLUTION; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; URANIUM; URANIUM ALLOYS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES

Optional Information

Contract/Grant/Project number
AC05-76RL01830
Funding organization
USDOE (United States)
Secondary number(s)
OSTIID--1339915