Analyzing the safety impact of containment inerting at Vermont Yankee
Includes bibliographical references
| Main Authors: | , , , |
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| Other Authors: | |
| Format: | Technical Report |
| Published: |
Cambridge, Mass. : Massachusetts Institute of Technology, [Dept. of Nuclear Engineering, 1980]
2014
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| Subjects: | |
| Online Access: | http://hdl.handle.net/1721.1/89741 |
| _version_ | 1826192992936919040 |
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| author | Heising, Carolyn D. (Carolyn DeLane), 1952- Lepervanche-Valencia, José Gregorio Pilat, E. E., 1937- Slifer, Bruce C. |
| author2 | Massachusetts Institute of Technology. Department of Nuclear Engineering |
| author_facet | Massachusetts Institute of Technology. Department of Nuclear Engineering Heising, Carolyn D. (Carolyn DeLane), 1952- Lepervanche-Valencia, José Gregorio Pilat, E. E., 1937- Slifer, Bruce C. |
| author_sort | Heising, Carolyn D. (Carolyn DeLane), 1952- |
| collection | MIT |
| description | Includes bibliographical references |
| first_indexed | 2024-09-23T09:32:19Z |
| format | Technical Report |
| id | mit-1721.1/89741 |
| institution | Massachusetts Institute of Technology |
| last_indexed | 2024-09-23T09:32:19Z |
| publishDate | 2014 |
| publisher | Cambridge, Mass. : Massachusetts Institute of Technology, [Dept. of Nuclear Engineering, 1980] |
| record_format | dspace |
| spelling | mit-1721.1/897412019-04-11T04:11:17Z Analyzing the safety impact of containment inerting at Vermont Yankee Heising, Carolyn D. (Carolyn DeLane), 1952- Lepervanche-Valencia, José Gregorio Pilat, E. E., 1937- Slifer, Bruce C. Massachusetts Institute of Technology. Department of Nuclear Engineering Yankee Atomic Electric Company TK9008.M41 N96 no.240 Vermont Yankee Nuclear Power Station (Vernon, Vt.) Boiling water reactors -- Cooling Boiling water reactors -- Safety measures Includes bibliographical references Final Report; July 1980 Post-accident hydrogen generation in BWR containments is analyzed as a function of engineered hydrogen control system, assumed either nitrogen inerting or air dilution. Fault tree analysis was applied to assess the failure probability per demand of each system. These failure rates were then combined with the probability of accidents producing various hydrogen generation rates to calculate the overall system hydrogen control probability. Results indicate that both systems render approximately the same overall hydrogen control probability (air dilution: .917 - .989; nitrogen inerting: .987 - .998). Drywell entries and unscheduled shutdowns were also analyzed to determine the impact on the total BWR accident risk as it relates to the decay heat removal system. Results indicate that inerting may increase the overall risk due to a possible increase in the number of unscheduled shutdowns due to a lessened operator ability to correct and identify "unidentified" leakage from the primary coolant system. Further, possible benefits of inerting due to reduced torus corrosion and fire risk in containment appear to be dominated by the possible operations related disbenefits. 2014-09-16T23:37:30Z 2014-09-16T23:37:30Z 1980 Technical Report http://hdl.handle.net/1721.1/89741 857467927 MITNE ; no. 240 123, A1-A9 pages application/pdf Cambridge, Mass. : Massachusetts Institute of Technology, [Dept. of Nuclear Engineering, 1980] |
| spellingShingle | TK9008.M41 N96 no.240 Vermont Yankee Nuclear Power Station (Vernon, Vt.) Boiling water reactors -- Cooling Boiling water reactors -- Safety measures Heising, Carolyn D. (Carolyn DeLane), 1952- Lepervanche-Valencia, José Gregorio Pilat, E. E., 1937- Slifer, Bruce C. Analyzing the safety impact of containment inerting at Vermont Yankee |
| title | Analyzing the safety impact of containment inerting at Vermont Yankee |
| title_full | Analyzing the safety impact of containment inerting at Vermont Yankee |
| title_fullStr | Analyzing the safety impact of containment inerting at Vermont Yankee |
| title_full_unstemmed | Analyzing the safety impact of containment inerting at Vermont Yankee |
| title_short | Analyzing the safety impact of containment inerting at Vermont Yankee |
| title_sort | analyzing the safety impact of containment inerting at vermont yankee |
| topic | TK9008.M41 N96 no.240 Vermont Yankee Nuclear Power Station (Vernon, Vt.) Boiling water reactors -- Cooling Boiling water reactors -- Safety measures |
| url | http://hdl.handle.net/1721.1/89741 |
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