WorldCat Identities

Crosthwaite, J. L.

Overview
Works: 10 works in 26 publications in 1 language and 67 library holdings
Genres: Architectural drawings 
Roles: Author
Classifications: TD898.13.C2, 621.4838
Publication Timeline
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Most widely held works by J. L Crosthwaite
Fuel characterization research for the Canadian Nuclear Fuel Waste Management Program by L. H Johnson( Book )

4 editions published between 1983 and 1984 in English and held by 17 WorldCat member libraries worldwide

Uranium carbide fuel for organic cooled reactors by Atomic Energy of Canada Limited( Book )

5 editions published between 1972 and 1973 in English and held by 12 WorldCat member libraries worldwide

FAST NEUTRON FACILITIES FOR WR-1 by J. L Crosthwaite( Book )

4 editions published between 1973 and 1974 in English and held by 11 WorldCat member libraries worldwide

Design, fabrication and testing of a prototype stressed-shell fuel isolation container by J. L Crosthwaite( Book )

4 editions published between 1976 and 1982 in English and held by 8 WorldCat member libraries worldwide

An experiment to examine the mechanistic behaviour of irradiated CANDU fuel stored under dry conditions by I. E Oldaker( )

4 editions published between 1976 and 1979 in English and held by 7 WorldCat member libraries worldwide

The performance assessment and ranking of container design options for the Canadian Nuclear Fuel Waste Management Program by J. L Crosthwaite( Book )

1 edition published in 1994 in English and held by 5 WorldCat member libraries worldwide

Technical specifications for a Concept Assessment Engineering Study (CAES) of a Used-Fuel Disposal Centre (UFDC) by Peter Baumgartner( Book )

1 edition published in 1993 in English and held by 3 WorldCat member libraries worldwide

A structural assessment of some alternative container designs for the disposal of CANDU used-fuel waste by J. D Garroni( Book )

1 edition published in 1996 in English and held by 2 WorldCat member libraries worldwide

The disposal of Canada's nuclear fuel waste : engineered barriers alternatives by Atomic Energy of Canada Limited( Book )

1 edition published in 1994 in English and held by 1 WorldCat member library worldwide

Preliminary analysis of the creep behaviour of nuclear fuel-waste container materials by R Dutton( Book )

1 edition published in 1996 in English and held by 1 WorldCat member library worldwide

Consideration of various container designs for use in underground disposal of nuclear fuel waste has identified either titanium or copper as the material suitable for constructing the container shell. As part of the research program to examine the structural integrity of the container, creep tests are being conducted on commercially pure titanium and oxygen-free copper. This report presents the preliminary data obtained and describes the evaluation of various constitutive equations to represent the creep curves, thus providing the basis for extrapolation of creep behaviour over the design lifetime of the container. In this regard, a specific focus is placed on equations derived from the theta projection concept. Results are also presented from metallographic examination of creep damage. The results are analyzed within the context of extant literature and their implications for future container design are discussed
 
Audience Level
0
Audience Level
1
  General Special  
Audience level: 0.00 (from 0.00 for Fuel chara ... to 0.00 for Fuel chara ...)

Languages
English (26)