| dc.contributor.author | Wei, Thomas Ying Chung | en_US |
| dc.contributor.author | Hansen Kent F. | en_US |
| dc.contributor.other | Massachusetts Institute of Technology. Department of Nuclear Engineering | en_US |
| dc.contributor.other | U.S. Atomic Energy Commission | en_US |
| dc.date.accessioned | 2014-09-12T23:51:56Z | |
| dc.date.available | 2014-09-12T23:51:56Z | |
| dc.date.issued | 1975 | en_US |
| dc.identifier.uri | http://hdl.handle.net/1721.1/89495 | |
| dc.description | Originally presented as the first author's thesis (Ph. D.), M.I.T. Dept. of Nuclear Engineering, 1975 | en_US |
| dc.description | Includes bibliographical references (pages 163-164) | en_US |
| dc.description.sponsorship | Energy Research and Development Agency report AT(11-1)-2262 | en_US |
| dc.format.extent | 311 pages | en_US |
| dc.publisher | Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975 | en_US |
| dc.relation.ispartofseries | MITNE ; no. 173 | en_US |
| dc.relation.ispartofseries | COO ; 2262-7 | en_US |
| dc.subject.lcc | TK9008.M41 N96 no.173 | en_US |
| dc.subject.lcsh | Finite element method | en_US |
| dc.subject.lcsh | Neutron transport theory | en_US |
| dc.subject.lcsh | Nuclear reactors -- Computer programs | en_US |
| dc.subject.lcsh | Nuclear reactor kinetics | en_US |
| dc.title | The finite element method for neutron diffusion problems in hexagonal geometry | en_US |
| dc.type | Technical Report | en_US |
| dc.identifier.oclc | 02340765 | en_US |
