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
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Format: | Technical Report |
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Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975
2014
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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 |
id | mit-1721.1/89495 |
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 |
record_format | dspace |
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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