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dc.contributor.authorShober, Robert Anthonyen_US
dc.contributor.authorHenry, Allan F.en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.otherElectric Power Research Instituteen_US
dc.date.accessioned2014-09-16T23:36:16Z
dc.date.available2014-09-16T23:36:16Z
dc.date.issued1976en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89731
dc.description"November, 1976."en_US
dc.descriptionAlso issued as a Ph. D. thesis written by the first author and supervised by the second author, MIT Dept. of Nuclear Engineering, 1977en_US
dc.descriptionIncludes bibliographical references (pages 112-116)en_US
dc.description.abstractThis thesis is concerned with methods for the transient solution of the neutron diffusion equations in one or two energy groups. Initially, nonlinear methods for solving the static diffusion equations using the finite element method were investigated. By formulating a new eigenvalue equation, some improvement in the solution efficiency was obtained. However, the transient solution of the diffusion equation using the finite element method was considered to be overly expensive. An analytic method for solving the one-dimensional diffusion equation was then developed. Numerical examples confirmed that this method is exact in one dimension. The method was extended to two dimensions, and results compared employing two different approximations for the transverse leakage. The method based on a flat approximation to the leakage was found to be superior, and it was extended to time-dependent problems. Results of time-dependent test problems show the procedure to be accurate and efficient. Comparisons with conventional finite difference techniques (such as TWIGL or MEKIN) indicate that the scheme can be an order of magnitude more cost effective.en_US
dc.format.extent159 pagesen_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1976]en_US
dc.relation.ispartofseriesMITNE ; no. 196en_US
dc.relation.ispartofseriesReport (Electric Power Research Institute)en_US
dc.subject.lccTK9008.M41 N96 no.196en_US
dc.subject.lcshNuclear reactors -- Tablesen_US
dc.subject.lcshFinite element methoden_US
dc.subject.lcshNeutron transport theoryen_US
dc.titleNonlinear methods for solving the diffusion equationen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc857233436en_US


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