Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report For November 1 1959 To January 31 1960
DOWNLOAD
Download Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report For November 1 1959 To January 31 1960 PDF/ePub or read online books in Mobi eBooks. Click Download or Read Online button to get Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report For November 1 1959 To January 31 1960 book now. This website allows unlimited access to, at the time of writing, more than 1.5 million titles, including hundreds of thousands of titles in various foreign languages. If the content not found or just blank you must refresh this page
Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report For November 1 1959 To January 31 1960
DOWNLOAD
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.).
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 elements categories.
Fuel Element Development Program For The Pebble Bed Reactor
DOWNLOAD
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
DOWNLOAD
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
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.
Pebble Bed Reactor Program
DOWNLOAD
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.
U S Government Research Reports
DOWNLOAD
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.
Nuclear Science Abstracts
DOWNLOAD
Author :
language : en
Publisher:
Release Date : 1960
Nuclear Science Abstracts 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 Nuclear energy categories.
Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report May 1 1960 July 31 1960
DOWNLOAD
Author :
language : en
Publisher:
Release Date : 1961
Fuel Element Development Program For The Pebble Bed Reactor Quarterly Progress Report May 1 1960 July 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 1961 with categories.
Fabrication of alumina-coated UO2 and pyrolytic carboncoated UC/ sub 2/ particles was studied. Some reaction was noted between alumina and graphite at 2500 deg F. For UC2 particles coated with carbon at 2000 deg F, the coatings were found to crack at temperaturss above 2000 deg F, whereas 2450 deg F deposition gave fewer failures at 3600 deg F, more rapid deposition- ratss, and absence of excess soot formation. A Pebble Bed Reactor fuel element consisting of a 1.5-in. graphite sphere fueled with alumina-coated UO2 particles was irradiated at 1400 deg F to a burrup of 3.3 at.% U235. Up to 2.5 at.% burnup, the fission product leakage factors (rate of release/rate of production) ranged between 10−9 and 10−5 for 10 isotopes and were ascribed to trace amounts of uranium contamination outside the particle coatings. In the latter part of the quarter, ths leakage factor for Xe133 rose to lO/ sup -3/ while several other shorter lived fission products increased to a smaller extent, indicating the beginning of diffusion through the coatings due to radiation damage of the alumina. Carbon-coated UC2 particles coated at 2000 deg F were found to have good fission product retention up to 2000 deg F, and less than 4.5 x 10−6 of the Xen133 was release d in a 4-hr test. Graphite bodies of density>2.0 g/cm3 were prepared using natural graphite powder as filler material, and their crushing strength was on the same order as that of AGOT synthetic graphite. (D.L.C.).
Ceramic Matrix Fuels Containing Coated Particles
DOWNLOAD
Author :
language : en
Publisher:
Release Date : 1962
Ceramic Matrix Fuels Containing Coated Particles written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with Ceramic coating categories.