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Title: Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material

A metal matrix composite (MMC) material comprised of hafnium aluminide (Al3Hf) intermetallic particles in an aluminum matrix has been identified as a promising material for fast-flux irradiation testing applications. This material can filter thermal neutrons while simultaneously providing high rates of conductive cooling for experiment capsules. Our purpose is to investigate effects of Hf-Al material composition and neutron irradiation on thermophysical properties, which were measured before and after irradiation. When performing differential scanning calorimetry (DSC) on the irradiated specimens, a large exotherm corresponding to material annealment was observed. Thus, a test procedure was developed to perform DSC and laser flash analysis (LFA) to obtain the specific heat and thermal diffusivity of pre- and post-annealment specimens. This paper presents the thermal properties for three states of the MMC material: (1) unirradiated, (2) as-irradiated, and (3) irradiated and annealed. Microstructure-property relationships were obtained for the thermal conductivity. These relationships are useful for designing components from this material to operate in irradiation environments. Furthermore, the ability of this material to effectively conduct heat as a function of temperature, volume fraction Al 3Hf, radiation damage and annealing is assessed using the MOOSE suite of computational tools.
Authors:
 [1] ;  [2]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. North Carolina State Univ., Raleigh, NC (United States). Dept. of Chemical and Biomolecular Engineering
Publication Date:
Report Number(s):
INL/JOU-16-37690
Journal ID: ISSN 2196-2936; PII: 76; TRN: US1702301
Grant/Contract Number:
AC07-05ID14517
Type:
Accepted Manuscript
Journal Name:
Metallurgical and Materials Transactions. E, Materials for Energy Systems
Additional Journal Information:
Journal Volume: 3; Journal Issue: 3; Journal ID: ISSN 2196-2936
Publisher:
ASM International
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; asymptotic expansion homogenization; finite-element analysis; neutron absorber; Thermal conductivity; irradiation experiment
OSTI Identifier:
1357606