PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2 PDF Download

Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2 PDF full book. Access full book title PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2 by . Download full books in PDF and EPUB format.

PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2

PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A series of preliminary irradiations has been made on ceramic fuels of interest for thermal reactors. Most of the studies were devoted to ThO/sub 2/-U0/ sub 2/ compositions because of certain advantages possessed by this material. ThO/sub 2/-2.5 wt.% U0/sub 2/ and ThO/sub 2/-10 wt.% pellets were irradiated bare and in stainless steel, Zircaloy, and aluminum alloy claddings, with the annulus between the ceramic pellets and the cladding filled with air, a helium -argon mixture, NaK, or lead. It was found that the ThO/sub 2/-U0/sub 2/ specimens were highly stable under irradiation. The U0/sub 2/ and U0/sub 2/-Zr specimens showed a relatively greater tendency to fracture during irradiation. Assemblies of ThO/ sub 2/-10 wt.% U0/sub 2/ pellets leadbonded to aluminum alloy cladding were found to be able to withstand higher heat fluxes without damage than similar assemblies with helium -argon bonding. (auth).

PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2

PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A series of preliminary irradiations has been made on ceramic fuels of interest for thermal reactors. Most of the studies were devoted to ThO/sub 2/-U0/ sub 2/ compositions because of certain advantages possessed by this material. ThO/sub 2/-2.5 wt.% U0/sub 2/ and ThO/sub 2/-10 wt.% pellets were irradiated bare and in stainless steel, Zircaloy, and aluminum alloy claddings, with the annulus between the ceramic pellets and the cladding filled with air, a helium -argon mixture, NaK, or lead. It was found that the ThO/sub 2/-U0/sub 2/ specimens were highly stable under irradiation. The U0/sub 2/ and U0/sub 2/-Zr specimens showed a relatively greater tendency to fracture during irradiation. Assemblies of ThO/ sub 2/-10 wt.% U0/sub 2/ pellets leadbonded to aluminum alloy cladding were found to be able to withstand higher heat fluxes without damage than similar assemblies with helium -argon bonding. (auth).

Preliminary Irradiations of the Ceramic Fuels UO2, UO2-Zr, and ThO2-UO2

Preliminary Irradiations of the Ceramic Fuels UO2, UO2-Zr, and ThO2-UO2 PDF Author: J. H. Kittel
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 36

Book Description