| dc.contributor.author | Huang, Y. (Yuhao) | en_US |
| dc.contributor.author | Siu, N. O. (Nathan O.) | en_US |
| dc.contributor.author | Lanning, David D. | en_US |
| dc.contributor.author | Carroll, John S., 1948- | en_US |
| dc.contributor.other | Massachusetts Institute of Technology. Department of Nuclear Engineering | en_US |
| dc.contributor.other | U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research | en_US |
| dc.date.accessioned | 2014-09-25T16:12:22Z | |
| dc.date.available | 2014-09-25T16:12:22Z | |
| dc.date.issued | 1990 | en_US |
| dc.identifier.uri | http://hdl.handle.net/1721.1/90349 | |
| dc.description | Statement of responsibility on title page reads: Y. Huang, N. Siu, D. Lanning ,and J. Carroll | en_US |
| dc.description | "June 1990." | en_US |
| dc.description | Includes bibliographical references (leaf 11) | en_US |
| dc.description.abstract | This report provides an analysis of the data collected during a one-month visit to a 2-unit, non-U.S. PWR. The data consist of results from interviews (largely with plant operators and former shift engineers) and from reviews of videotapes covering crew responses to steam generator tube rupture training exercises. The interviews were aimed at indicating perceptions of individual and group skills. The analysis shows that the interview results are fairly consistent, that the time required to perform key actions does not generally correlate very well with the team quality ratings obtained from the interviews, and that the team quality ratings obtained from interviews correlate reasonably with ratings of the team performances (during the exercises) developed using the 7-dimension scale described in PNL-7250. | en_US |
| dc.description.sponsorship | Supported by the Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission NRC-04-89-356 | en_US |
| dc.format.extent | 20 leaves | en_US |
| dc.publisher | Cambridge, MA : Nuclear Engineering Dept., Massachusetts Institute of Technology, 1990 | en_US |
| dc.relation.ispartofseries | MITNE ; 290 | en_US |
| dc.subject.lcc | TK9008.M41 N96 no.290 | en_US |
| dc.subject.lcsh | Pressurized water reactors -- Loss of coolant -- Simulation methods | en_US |
| dc.subject.lcsh | Pressurized water reactors -- Accidents -- Simulation methods | en_US |
| dc.title | Data analysis : operating crew characteristics and interactions during steam generator tube rupture simulation | en_US |
| dc.type | Technical Report | en_US |
| dc.identifier.oclc | 22194982 | en_US |
