Fuel Element Development Program For The Pebble Bed Reactor
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Fuel Element Development Program For The Pebble Bed Reactor
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Author :
language : en
Publisher:
Release Date : 1961
Fuel Element Development Program For The Pebble Bed Reactor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Nuclear fuel elements categories.
Fuel Element Development Program For The Pebble Bed Reactor
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Author :
language : en
Publisher:
Release Date : 1959
Fuel Element Development Program For The Pebble Bed Reactor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Nuclear fuel claddings categories.
Fuel Element Development Program For The Pebble Bed Reactor
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Author : Sanderson & Porter, Inc
language : en
Publisher:
Release Date : 1959
Fuel Element Development Program For The Pebble Bed Reactor written by Sanderson & Porter, Inc and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Nuclear fuel elements categories.
Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1-1/2 in diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and feul particle coatings such as alumina. Low diffusion product leakage rates at high temperatures have been observed for some of these coatings. High level irradiation damage to either the silicon carbide coating or the coating-graphite bond.
Fuel Element Development Program For The Pebble Bed Reactor
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Author :
language : en
Publisher:
Release Date : 1961
Fuel Element Development Program For The Pebble Bed Reactor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Nuclear fuel claddings categories.
Fuel Element Development Program For The Pebble Bed Reactor
DOWNLOAD
Author :
language : en
Publisher:
Release Date : 1960
Fuel Element Development Program For The Pebble Bed Reactor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Coatings categories.
Fuel Element Development Program For The Pebble Bed Reactor Final Report
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Author :
language : en
Publisher:
Release Date :
Fuel Element Development Program For The Pebble Bed Reactor Final Report written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on with categories.
The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found-that molecularly deposited'' ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces and where a larger thickness-todiameter ratio could be used than if the coating were on the surface of the graphite sphere. Fuel elements were irradiated to burnups ranging up to about 6 at.% U235. In all specimens containing a uniform dispersion of fuel, the graphite spheres were found to retain their structural properties after irradiation. Data are given on fuel particle coatings of A12O3, pyrolytic carbon, and metals: surface coatings of siliconized silicon carbide, pyrolytic carbon, and metal carbides; properties of and the effects of irradiation on graphite spheres; the use of natural graphite in preparing a high-density matrix material; graphite fueling by thorium nitrate infiltration; subsurface metal and metal carbide coatings for graphite; and an in-pile loop program on the behavior of fission products in a recycle helium stream. (auth).
Fuel Element Development Program For The Pebble Bed Reactor A Topical Report On Sub Surface Coatings For Fueled Graphite Spheres
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Author :
language : en
Publisher:
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Fuel Element Development Program For The Pebble Bed Reactor A Topical Report On Sub Surface Coatings For Fueled Graphite Spheres written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on with categories.
An exploratory program on subsurface coatin8s for graphite fuel elements is summarized. A number of coatings with various melting points which could be located beneath the surface of a fueled graphite sphere were investigated. Of the materials with lower melting points. nickel and a special glass compound appeared to form continuous coatings when a hot-pressing technique was employed. Several materials with high melting points. such as Ti, Cr, and MoSi2, showed some promise, even though present equipment limitations prevented these specimens from being hot-pressed at the melting point of the coating. (W.L.H.).
The Pebble Bed Reactor Program Current Fuel Element Developments And Their Effects On The Pebble Bed Reactor Development Program
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Author :
language : en
Publisher:
Release Date : 1960
The Pebble Bed Reactor Program Current Fuel Element Developments And Their Effects On The Pebble Bed Reactor Development Program written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with categories.
Recent fuel element irradiations demonstrated the structural integrity of spherical uranium-graphite fuel elements at burn-ups in excess of the design requirements of a 125 Mw(e) Pebble Bed Reactor (PBR) power plant. Other irradiations indicated the successful development of a coated fuel particle which permits fabrication of fuel elements meeting the PBR design objectives of a fission-product release rate (R/B)? 1°−6. beta plus gamma system activity in a 125 Mw(e) PBR is 490 c, assuming complete release of /sup lO-6/ of all fission products volatile at or below 2500 deg F. The low R/B being obtained from PBR fuel elements indicates that decay during diffusion of the short-lived volatile precursors of nonvolatile daughter products will result in further reduction of this system activity, and an increase in the average half life of the fission products remaining in the system will increase the efficiency of a bypass clean-up system. The method of fabricating coated particles by the hydrolysis of metallic chlorides to produce oxides or pyrolysis of hydrocarbons to produce carbon on a suitable substrate, is described, and preirradiation test results are given. An accelerated coated-fuel-particle program is discussed as well as development work on the Pebble Bed REactor concept as a whole. auth.
Fuel Element Development Program For The Pebble Bed Reactor Phase I Progress Report For May 1 1959 To October 31 1959
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Author :
language : en
Publisher:
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Fuel Element Development Program For The Pebble Bed Reactor Phase I Progress Report For May 1 1959 To October 31 1959 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on with categories.
Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1 1/2 in. diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and fuel particle coatings such as alumina. Low fission product leakage rates at high temperatures have been observed for some of these coatings. High-level irradiation has given no visible evidence of radiation damage to either the silicon carbide coating or the coating-graphite bond. (auth).
Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report For November 1 1959 To January 31 1960
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Author :
language : en
Publisher:
Release Date : 1960
Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report For November 1 1959 To January 31 1960 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with categories.
A variety of spherical uranium--graphite fuel elements for the Pebble Bed Reactor (PBR) was fabricated. Poor results with sintered alumina coated UO/ sub 2/ particles led to the development of slumina coating by vspor deposition, for which good results have been obtained. A variety of sub-surface metal, metal carbide, and ceramic coatings located between an unfueled graphite shell and the fueled core of a PBR fuel element was prepared and examined. Most of the materials and processes showed poor results. Excellent metal recoveries were achieved from the metal oxide--graphite system using the grind-leach technique of reprocessing. Test results on Si-- SiC coated fuel elements showed good fission product retention in neutron activation tests, a self-welding tendency between adjacent spheres at 2500 deg F surface temperature, and no evidence of failure when an interanl gas pressure of 300 psi was applied. Fission product release rates from a pyrolytic carbon coated specimen under low-level irradiation were obtained at 150 to 1900 deg F. The design of the in-pile loop to study the behavior of fission products escaping from PBR fuel elements wss established. (C.J.G.).