Performance of (U,Zr)C-graphite (composite) and of (U,Zr)C (carbide) fuel elements in the Nuclear Furnace 1 test reactor

Technical Report · Sat Sep 01 04:00:00 EDT 1973

DOI:https://doi.org/10.2172/4419566· OSTI ID:4419566

Lyon, L L

The properties of and reactor test results for two types of nuclear- propulsion-reactor fuel elements containing uraniumzirconium carbide, (U,Zr)C, are reported. Composite fuel elements containing graphite and ~35 vol% carbide, along with fuel elements consisting only of carbide, were tested in Los Alamos Scientific Laboratory's Nuclear Furnace 1 reactor for l09 min at peak power densities of ~4500 MW/m/sup 3/ and temperature up to 2500 deg K. Fission-fragment damage to the graphite phase of the composite fuel elements increased the roomtemperature thermal resistivity of the matrix ninefold, resulting in unexpected high mass losses of carbon. The carbide elements developed both longitudinal and transverse fractures but did not fragment into small-size particles. (auth)

• Research Organization: Los Alamos Scientific Lab., N.Mex. (USA)
• DOE Contract Number: W-7405-ENG-36
• NSA Number: NSA-29-009421
• OSTI ID: 4419566
• Report Number(s): LA--5398-MS
• Country of Publication: United States
• Language: English

Related Subjects

*NUCLEAR FURNACE REACTOR-- FUEL ELEMENTS
*URANIUM CARBIDES-- PHYSICAL RADIATION EFFECTS
*ZIRCONIUM CARBIDES-- PHYSICAL RADIATION EFFECTS
N50140 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N77800* --Reactors--Space
Mobile
Propulsion
Transportation & Package Reactors
PERFORMANCE TESTING
POWER DENSITY
VERY HIGH TEMPERATURE