Generalized computer codes were devised for solving stress problems of some complexity. These codes were applied to stress problsms relating to the graphite moderator elements in the Experimental Gas-cooled Reactor. The stress relief obtained by aubdividing the moderator elements was evaluated. The distontion and bending moments of the elements were also determined. (auth)
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Battelle Memorial Inst., Columbus, Ohio
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Generalized computer codes were devised for solving stress problems of some complexity. These codes were applied to stress problsms relating to the graphite moderator elements in the Experimental Gas-cooled Reactor. The stress relief obtained by aubdividing the moderator elements was evaluated. The distontion and bending moments of the elements were also determined. (auth)
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Redmond, R.F.; Hulbert, L.E. & Clark, R.W.NUMERICAL SOLUTION OF REACTOR STRESS PROBLEMS,
report,
February 28, 1961;
Columbus, Ohio.
(https://digital.library.unt.edu/ark:/67531/metadc871257/:
accessed September 9, 2024),
University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu;
crediting UNT Libraries Government Documents Department.
