| dc.contributor.author | Sovka, Jerry Alois | en_US |
| dc.contributor.author | Benedict, Manson | en_US |
| dc.contributor.other | Massachusetts Institute of Technology. Department of Nuclear Engineering | en_US |
| dc.contributor.other | Massachusetts Institute of Technology. Computation Center | en_US |
| dc.contributor.other | U.S. Atomic Energy Commission | en_US |
| dc.date.accessioned | 2014-09-16T23:38:34Z | |
| dc.date.available | 2014-09-16T23:38:34Z | |
| dc.date.issued | 1963 | en_US |
| dc.identifier.uri | http://hdl.handle.net/1721.1/89756 | |
| dc.description | "This work was done in part at the M.I.T. Computation Center, Cambridge, Massachusetts." | en_US |
| dc.description | "MIT-2073-3." | en_US |
| dc.description | Includes bibliographical references (leaf 34) | en_US |
| dc.description | Progress report; September 1964 | en_US |
| dc.description.abstract | Further modifications to the fuel cycle code FUELMOVE are described which were made in an attempt to obtain results for reflected reactors operated under batch, outin, and bidirectional fueling schemes. Numerical methods used to obtain solutions to the condensed two-group diffusion equation are presented. Results indicated that the method for obtaining solutions for the thermal flux distribution in reflected reactors using this condensed two-group formulation appears to be inadequate in certain cases in which the reactor is treated explicitly as a separate region. A recommendation is made for one additional evaluation of this technique with a further recommendation that subsequent studies of the fuel cycle behavior of reflected reactors be made using the full two-group diffusion formulation. | en_US |
| dc.description.sponsorship | Progress report work done under contract with U.S. Atomic Energy Commission AT(30-1)-2073 | en_US |
| dc.format.extent | [iii], 34 leaves | en_US |
| dc.publisher | [Cambridge, Mass.] Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963 | en_US |
| dc.relation.ispartofseries | MIT-2073-3 | en_US |
| dc.relation.ispartofseries | MITNE ; no. 58 | en_US |
| dc.subject.lcc | TK9008.M41 N96 no.58 | en_US |
| dc.subject.lcsh | Nuclear fuel elements | en_US |
| dc.subject.lcsh | Nuclear reactors -- Computer programs | en_US |
| dc.title | Fuel cycle code, "FUELMOVE III" | en_US |
| dc.title.alternative | FUELMOVE | en_US |
| dc.type | Technical Report | en_US |
| dc.identifier.oclc | 857918073 | en_US |
