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

Abstract

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)

Authors:
Publication Date:
Research Org.:
Los Alamos Scientific Lab., N.Mex. (USA)
OSTI Identifier:
4419566
Report Number(s):
LA-5398-MS
NSA Number:
NSA-29-009421
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 30-JUN-74
Country of Publication:
United States
Language:
English
Subject:
N77800* -Reactors-Space, Mobile, Propulsion, Transportation & Package Reactors; N50140 -Metals, Ceramics, & Other Materials-Ceramics & Cermets-Radiation Effects; *NUCLEAR FURNACE REACTOR- FUEL ELEMENTS; *URANIUM CARBIDES- PHYSICAL RADIATION EFFECTS; *ZIRCONIUM CARBIDES- PHYSICAL RADIATION EFFECTS; PERFORMANCE TESTING; POWER DENSITY; VERY HIGH TEMPERATURE

Citation Formats

Lyon, L L. Performance of (U,Zr)C-graphite (composite) and of (U,Zr)C (carbide) fuel elements in the Nuclear Furnace 1 test reactor. United States: N. p., 1973. Web. doi:10.2172/4419566.
Lyon, L L. Performance of (U,Zr)C-graphite (composite) and of (U,Zr)C (carbide) fuel elements in the Nuclear Furnace 1 test reactor. United States. doi:10.2172/4419566.
Lyon, L L. Sat . "Performance of (U,Zr)C-graphite (composite) and of (U,Zr)C (carbide) fuel elements in the Nuclear Furnace 1 test reactor". United States. doi:10.2172/4419566. https://www.osti.gov/servlets/purl/4419566.
@article{osti_4419566,
title = {Performance of (U,Zr)C-graphite (composite) and of (U,Zr)C (carbide) fuel elements in the Nuclear Furnace 1 test reactor},
author = {Lyon, L L},
abstractNote = {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)},
doi = {10.2172/4419566},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1973},
month = {9}
}