The finite element method for neutron diffusion problems in hexagonal geometry

Originally presented as the first author's thesis (Ph. D.), M.I.T. Dept. of Nuclear Engineering, 1975

Bibliographic Details
Main Authors: Wei, Thomas Ying Chung, Hansen Kent F.
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Engineering
Format: Technical Report
Published: Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975 2014
Subjects:
Online Access:http://hdl.handle.net/1721.1/89495
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author Wei, Thomas Ying Chung
Hansen Kent F.
author2 Massachusetts Institute of Technology. Department of Nuclear Engineering
author_facet Massachusetts Institute of Technology. Department of Nuclear Engineering
Wei, Thomas Ying Chung
Hansen Kent F.
author_sort Wei, Thomas Ying Chung
collection MIT
description Originally presented as the first author's thesis (Ph. D.), M.I.T. Dept. of Nuclear Engineering, 1975
first_indexed 2024-09-23T11:34:40Z
format Technical Report
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institution Massachusetts Institute of Technology
last_indexed 2024-09-23T11:34:40Z
publishDate 2014
publisher Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975
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spelling mit-1721.1/894952019-04-10T09:42:50Z The finite element method for neutron diffusion problems in hexagonal geometry Wei, Thomas Ying Chung Hansen Kent F. Massachusetts Institute of Technology. Department of Nuclear Engineering U.S. Atomic Energy Commission TK9008.M41 N96 no.173 Finite element method Neutron transport theory Nuclear reactors -- Computer programs Nuclear reactor kinetics Originally presented as the first author's thesis (Ph. D.), M.I.T. Dept. of Nuclear Engineering, 1975 Includes bibliographical references (pages 163-164) Energy Research and Development Agency report AT(11-1)-2262 2014-09-12T23:51:56Z 2014-09-12T23:51:56Z 1975 Technical Report http://hdl.handle.net/1721.1/89495 02340765 MITNE ; no. 173 COO ; 2262-7 311 pages application/pdf Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975
spellingShingle TK9008.M41 N96 no.173
Finite element method
Neutron transport theory
Nuclear reactors -- Computer programs
Nuclear reactor kinetics
Wei, Thomas Ying Chung
Hansen Kent F.
The finite element method for neutron diffusion problems in hexagonal geometry
title The finite element method for neutron diffusion problems in hexagonal geometry
title_full The finite element method for neutron diffusion problems in hexagonal geometry
title_fullStr The finite element method for neutron diffusion problems in hexagonal geometry
title_full_unstemmed The finite element method for neutron diffusion problems in hexagonal geometry
title_short The finite element method for neutron diffusion problems in hexagonal geometry
title_sort finite element method for neutron diffusion problems in hexagonal geometry
topic TK9008.M41 N96 no.173
Finite element method
Neutron transport theory
Nuclear reactors -- Computer programs
Nuclear reactor kinetics
url http://hdl.handle.net/1721.1/89495
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