| dc.contributor.advisor | David D. Lanning. | en_US |
| dc.contributor.author | Bernard, John Albert | en_US |
| dc.date.accessioned | 2005-08-04T15:33:24Z | |
| dc.date.available | 2005-08-04T15:33:24Z | |
| dc.date.copyright | 1979 | en_US |
| dc.date.issued | 1979 | en_US |
| dc.identifier.uri | http://hdl.handle.net/1721.1/15980 | |
| dc.description | Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1979. | en_US |
| dc.description | MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. | en_US |
| dc.description | Includes bibliographical references. | en_US |
| dc.description.statementofresponsibility | by John A. Bernard, Jr. | en_US |
| dc.format.extent | 2 v. (826 leaves) | en_US |
| dc.format.extent | 49885326 bytes | |
| dc.format.extent | 49885082 bytes | |
| dc.format.mimetype | application/pdf | |
| dc.format.mimetype | application/pdf | |
| dc.language.iso | eng | en_US |
| dc.publisher | Massachusetts Institute of Technology | en_US |
| dc.relation.ispartofseries | Massachusetts Institute of Technology. Dept. of Nuclear Engineering. | en_US |
| dc.rights | M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission. | en_US |
| dc.rights.uri | http://dspace.mit.edu/handle/1721.1/7582 | |
| dc.subject | Nuclear Engineering | en_US |
| dc.subject.lcsh | Nuclear fuel elements Computer programs | en_US |
| dc.subject.lcsh | Neutron transport theory | en_US |
| dc.subject.lcsh | Nuclear fuels | en_US |
| dc.title | MITR-II fuel management, core depletion, and analysis : codes developed for the diffusion theory program CITATION | en_US |
| dc.type | Thesis | en_US |
| dc.description.degree | Nucl.E. | en_US |
| dc.contributor.department | Massachusetts Institute of Technology. Department of Nuclear Engineering | en_US |
| dc.contributor.department | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering | |
| dc.identifier.oclc | 07060926 | en_US |
