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Title: DEVELOPMENT OF FUELED GRAPHITE CONTAINING PYROLYTIC-CARBON COATED CARBIDE PARTICLES FOR NONPURGED, GAS-COOLED REACTOR SYSTEMS

Abstract

From American Nuclear Society Meeting, New York, Nov. 1963. Progress is reported in several areas of development of fueled graphite containing coated particles for nonpurged gas-cooled reactor systems. The sol-gel process has been modified for making spherical particles of both thorium-uranium carbide and thorium-uranium oxide suitable for coating. Equipment has been assembled and methods have been developed for deposition of pyrolytic-carbon coatings under well-controlled conditions. Damage to coated particles during fabrication into a graphite matrix depends on the molding pressure and the volumetric content of coated particles. Vendor-supplied coated particles and fueled graphite spheres have been evaluated extensively in both inand out-of-reactor tests. Duplex- and triplex-coated particles have excellent fission-gas retention at 2050 deg F to burnups of l5 at.%, and one triplex sample has also shown good retention at 2500 deg F to 20 at.% burnup. Fueled graphite spheres containing coated particles have good irradiation performance, but the fission-gas release rates are somewhat higher than for unsupported coated particles. Fueled graphite spheres react with water vapor about as rapidiy as do Speer Mod-2 and ATJ grades of graphite. The diffusion rates in pyrolytic carbon are the same for uranium, thorium, and protactinium. The diffusion rates in the direction parallelmore » to the deposition plane are much higher than those in the perpendicular direction. (auth)« less

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., Tenn.
OSTI Identifier:
4110310
Report Number(s):
CONF-187-44
NSA Number:
NSA-18-012596
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-64
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; ABSORPTION; BURNUP; CARBIDES; CARBON; CASTING; CHEMICAL REACTIONS; COATING; CONFIGURATION; CONTROL; DEGASSING; DIFFUSION; FABRICATION; FAILURES; FISSION PRODUCTS; FUELS; GAS COOLANT; GRAPHITE; GRAPHITE ATJ; HIGH TEMPERATURE; IRRADIATION; LAYERS; MACHINE PARTS; MATERIALS TESTING; PERFORMANCE; PLANNING; PRESSURE; PROTACTINIUM; PYROLYSIS; REACTORS; SAMPLING; SOL-GEL PROCESS; SPHERES; THORIUM; THORIUM CARBIDES; THORIUM OXIDES; URANIUM; URANIUM CARBIDES; URANIUM OXIDES; VAPORS; VOLUME; WATER

Citation Formats

Carlsen, Jr, F L, Bomar, E S, and Harms, W.O. comp. DEVELOPMENT OF FUELED GRAPHITE CONTAINING PYROLYTIC-CARBON COATED CARBIDE PARTICLES FOR NONPURGED, GAS-COOLED REACTOR SYSTEMS. United States: N. p., 1963. Web.
Carlsen, Jr, F L, Bomar, E S, & Harms, W.O. comp. DEVELOPMENT OF FUELED GRAPHITE CONTAINING PYROLYTIC-CARBON COATED CARBIDE PARTICLES FOR NONPURGED, GAS-COOLED REACTOR SYSTEMS. United States.
Carlsen, Jr, F L, Bomar, E S, and Harms, W.O. comp. Tue . "DEVELOPMENT OF FUELED GRAPHITE CONTAINING PYROLYTIC-CARBON COATED CARBIDE PARTICLES FOR NONPURGED, GAS-COOLED REACTOR SYSTEMS". United States.
@article{osti_4110310,
title = {DEVELOPMENT OF FUELED GRAPHITE CONTAINING PYROLYTIC-CARBON COATED CARBIDE PARTICLES FOR NONPURGED, GAS-COOLED REACTOR SYSTEMS},
author = {Carlsen, Jr, F L and Bomar, E S and Harms, W.O. comp.},
abstractNote = {From American Nuclear Society Meeting, New York, Nov. 1963. Progress is reported in several areas of development of fueled graphite containing coated particles for nonpurged gas-cooled reactor systems. The sol-gel process has been modified for making spherical particles of both thorium-uranium carbide and thorium-uranium oxide suitable for coating. Equipment has been assembled and methods have been developed for deposition of pyrolytic-carbon coatings under well-controlled conditions. Damage to coated particles during fabrication into a graphite matrix depends on the molding pressure and the volumetric content of coated particles. Vendor-supplied coated particles and fueled graphite spheres have been evaluated extensively in both inand out-of-reactor tests. Duplex- and triplex-coated particles have excellent fission-gas retention at 2050 deg F to burnups of l5 at.%, and one triplex sample has also shown good retention at 2500 deg F to 20 at.% burnup. Fueled graphite spheres containing coated particles have good irradiation performance, but the fission-gas release rates are somewhat higher than for unsupported coated particles. Fueled graphite spheres react with water vapor about as rapidiy as do Speer Mod-2 and ATJ grades of graphite. The diffusion rates in pyrolytic carbon are the same for uranium, thorium, and protactinium. The diffusion rates in the direction parallel to the deposition plane are much higher than those in the perpendicular direction. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4110310}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {1}
}

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