| dc.contributor.author | Yarman, Nuh Tolga | en_US |
| dc.contributor.author | Henry, Allan F. | en_US |
| dc.contributor.author | Lanning, David D. | en_US |
| dc.contributor.author | Gosnell, James Waterbury | en_US |
| dc.contributor.other | Massachusetts Institute of Technology. Department of Nuclear Engineering | en_US |
| dc.date.accessioned | 2014-09-16T23:33:44Z | |
| dc.date.available | 2014-09-16T23:33:44Z | |
| dc.date.issued | 1972 | en_US |
| dc.identifier.uri | http://hdl.handle.net/1721.1/89717 | |
| dc.description | Statement of responsibility on title page reads: Nuh Tolga Yarman A.F. Henry, D.D. Lanning, and J.W. Gosnell | en_US |
| dc.description | "July 1972." | en_US |
| dc.description | Originally written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineering, 1972 | en_US |
| dc.description | Includes bibliographical references (pages [191]-193) | en_US |
| dc.description.abstract | The two-dimensional, time dependent, three-group diffusion equations for the proposed designed core of the MIT reactor are written with an extra source term accounting for the photoneutrons generated in the D20 reflector. An analytical expression is developed for this term. Then an approximate flux composed of two spatial shapes chosen beforehand, each having an unknown time coefficient, is inserted into the time dependent multigroup equations and the weighted residual criteria is applied. This yields multimode kinetics equations with generalized definitions for the conventional matrix parameters: generation time, reactivity, delayed neutron (and photoneutron) fractions matrices. Computational methods for these parameters are presented. An accident concerning the withdrawal of the shim rods is examined with the code OZAN written for the purpose of-the computations required by the present work. This study suggests that a space-dependent analysis is required to analyse the accident postulated. | en_US |
| dc.format.extent | 434 pages | en_US |
| dc.publisher | Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972] | en_US |
| dc.relation.ispartofseries | MITNE ; no. 139 | en_US |
| dc.subject.lcc | TK9008.M41 N96 no.139 | en_US |
| dc.subject.lcsh | Massachusetts Institute of Technology. Research Reactor | en_US |
| dc.subject.lcsh | Nuclear reactors | en_US |
| dc.subject.lcsh | Nuclear fuels | en_US |
| dc.title | The Reactivity and transient analysis of MITR-II | en_US |
| dc.type | Technical Report | en_US |
| dc.identifier.oclc | 856906474 | en_US |
