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Title: Chemical Engineering Division reactor fuels and materials chemistry research: July 1976--September 1977. [LMFBR; GCFR]

Technical Report ·
DOI:https://doi.org/10.2172/6107792· OSTI ID:6107792

Reactor safety studies were directed primarily toward obtaining high-temperature physical property data for use in reactor safety analyses. Spectroscopic data and an oxygen-potential model were used to calculate thermodynamic properties applicable to the equations of state of (U,Pu)O/sub 2/ and UO/sub 2/. Work was continued on the compilation of standard sets of property data on reactor fuels and materials. The viscosity of molten alumina and the thermal diffusivity of molten UO/sub 2/ were measured as functions of temperature. Modeling and chemical-interaction studies related to post-accident heat removal were conducted. The efforts in sodium technology supported the LMFBR program. Studies were conducted to explore the feasibility of upgrading the quality of commercial-grade sodium and sodium from decommissioned reactors to provide new sources of reactor-grade sodium. Work was started on the development of methods for disposal of contaminated alkali--metal wastes. In work related to tritium, a model was developed to describe the behavior of tritium in an LMFBR, tritium permeation through steam-generator materials was measured, and an in-sodium tritium meter was developed and tested in reactor environments. Work in the area of fuels and materials chemistry was conducted in support of the GCFR program. Portions of the cesium--uranium--oxygen phase diagram were investigated to aid in understanding the reaction of fission-product cesium with urania blanket material, particularly in relation to axial gas flow in vented GCFR fuel pins. Data on the oxidation of vanadium, niobium, and titanium were assessed to determine the suitability of these materials for use in controlling oxidative attack of stainless steel cladding.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
6107792
Report Number(s):
ANL-78-15
Country of Publication:
United States
Language:
English