LEU-Mo Fuel Out-of-Pile Characterization for TUM (Final Report)

Technical Report · Mon Sep 15 04:00:00 EDT 2014

DOI:https://doi.org/10.2172/1452880· OSTI ID:1452880

Burkes, Douglas E. ^[1]; Casella, Amanda J. ^[1]; Buck, Edgar C. ^[1]; Casella, Andrew M. ^[1]; Edwards, Matthew K. ^[1]; MacFarlan, Paul J. ^[1]; Pool, Karl N. ^[1]; Smith, Frances N. ^[1]; Steen, Franciska H. ^[1]

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

The Technische Universität München (TUM) located in Germany requested that Pacific Northwest National Laboratory (PNNL) perform thermal-physical property measurement services for determining the thermal conductivities of irradiated U-Mo dispersion fuel samples. Two dispersion fuel segments containing U-7Mo dispersion fuel in an Al-2wt% Si matrix harvested from the AFIP-1 irradiation experiment were provided to PNNL for this effort. The segments were sectioned into samples for pycnometry (density) and laser flash analysis (thermal diffusivity), differential scanning calorimetry (specific heat capacity), and optical metallography (thickness, image analysis). This report summarizes the findings of the analysis performed at TUM’s request.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 1452880
• Report Number(s): PNNL--23620; 600301020
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Uranium-molybdenum
dispersion
nuclear fuel
thermal properties