dc.contributor.author | Sims, Randal Nee. | en_US |
dc.date.accessioned | 2005-08-02T20:41:41Z | |
dc.date.available | 2005-08-02T20:41:41Z | |
dc.date.copyright | 1977 | en_US |
dc.date.issued | 1977 | en_US |
dc.identifier.uri | http://hdl.handle.net/1721.1/16407 | en_US |
dc.description | Thesis: Sc. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977 | en_US |
dc.description | Vita. | en_US |
dc.description | Includes bibliographical references. | en_US |
dc.format.extent | 224 leaves | en_US |
dc.publisher | Massachusetts Institute of Technology | en_US |
dc.rights | MIT theses may be protected by copyright. Please reuse MIT thesis content according to the MIT Libraries Permissions Policy, which is available through the URL provided. | en_US |
dc.rights.uri | http://dspace.mit.edu/handle/1721.1/7582 | en_US |
dc.subject | Nuclear Engineering | en_US |
dc.subject.lcsh | Nuclear reactor kinetics. | en_US |
dc.subject.lcsh | Neutron transport theory. | en_US |
dc.subject.other | Neutron transport theory. fast | en_US |
dc.subject.other | Nuclear reactor kinetics. fast | en_US |
dc.title | A coarse-mesh nodal diffusion method based on response matrix considerations. | en_US |
dc.type | Thesis | en_US |
dc.description.degree | Sc. D. | en_US |
dc.contributor.department | Massachusetts Institute of Technology. Department of Nuclear Engineering | en_US |
dc.identifier.oclc | 03793923 | en_US |
dc.description.collection | Sc. D. Massachusetts Institute of Technology, Department of Nuclear Engineering | en_US |
dspace.imported | 2024-04-19T16:26:38Z | en_US |