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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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 Phase I Progress Report For May 1 1959 To October 31 1959
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Author :
language : en
Publisher:
Release Date :
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
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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
DOWNLOAD
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.
U S Government Research Reports
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Author :
language : en
Publisher:
Release Date : 1961
U S Government Research Reports 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 Science categories.
Pebble Bed Reactor Program
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Author : U.S. Atomic Energy Commission
language : en
Publisher:
Release Date : 1961
Pebble Bed Reactor Program written by U.S. Atomic Energy Commission and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with categories.
Monthly Catalog Of United States Government Publications
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Author :
language : en
Publisher:
Release Date : 1961
Monthly Catalog Of United States Government Publications 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 Government publications categories.
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.).
List
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Author :
language : en
Publisher:
Release Date : 1948
List written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1948 with Nuclear energy categories.