Calculating failure probabilities of passive systems during transients
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.
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Format: | Thesis |
Language: | eng |
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Massachusetts Institute of Technology
2008
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Online Access: | http://hdl.handle.net/1721.1/41308 |
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author | Mackay, Francisco J |
author2 | George E. Apostolakis. |
author_facet | George E. Apostolakis. Mackay, Francisco J |
author_sort | Mackay, Francisco J |
collection | MIT |
description | Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007. |
first_indexed | 2024-09-23T14:47:59Z |
format | Thesis |
id | mit-1721.1/41308 |
institution | Massachusetts Institute of Technology |
language | eng |
last_indexed | 2024-09-23T14:47:59Z |
publishDate | 2008 |
publisher | Massachusetts Institute of Technology |
record_format | dspace |
spelling | mit-1721.1/413082019-04-11T06:10:59Z Calculating failure probabilities of passive systems during transients Mackay, Francisco J George E. Apostolakis. Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. Nuclear Science and Engineering. Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007. Includes bibliographical references (p. 45-46). A time-dependent reliability evaluation of a two-loop passive Decay Heat Removal (DHR) system was performed as part of the iterative design process for a helium-cooled fast reactor. The system was modeled using RELAP5-3D. The uncertainties in input parameters were assessed and were propagated through the model using Latin Hypercube Sampling. An important finding was the discovery that the smaller pressure loss through the DHR heat exchanger than through the core would make the flow to bypass the core through one DHR loop, if two loops operated in parallel. This finding is a warning against modeling only one lumped DHR loop and assuming that n of them will remove n times the decay power. Sensitivity analyses revealed that there are values of some input parameters for which failures are very unlikely. The calculated conditional (i.e., given the LOCA) failure probability was deemed to be too high leading to the identification of several design changes to improve system reliability. This study is an example of the kinds of insights that can be obtained by including a reliability assessment in the design process. It is different from the usual use of PSA in design, which compares different system configurations, because it focuses on the thermal-hydraulic performance of a safety function. by Francisco J. Mackay. S.M. 2008-04-23T14:44:05Z 2008-04-23T14:44:05Z 2007 2007 Thesis http://hdl.handle.net/1721.1/41308 214327612 eng M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission. http://dspace.mit.edu/handle/1721.1/7582 171 p. application/pdf Massachusetts Institute of Technology |
spellingShingle | Nuclear Science and Engineering. Mackay, Francisco J Calculating failure probabilities of passive systems during transients |
title | Calculating failure probabilities of passive systems during transients |
title_full | Calculating failure probabilities of passive systems during transients |
title_fullStr | Calculating failure probabilities of passive systems during transients |
title_full_unstemmed | Calculating failure probabilities of passive systems during transients |
title_short | Calculating failure probabilities of passive systems during transients |
title_sort | calculating failure probabilities of passive systems during transients |
topic | Nuclear Science and Engineering. |
url | http://hdl.handle.net/1721.1/41308 |
work_keys_str_mv | AT mackayfranciscoj calculatingfailureprobabilitiesofpassivesystemsduringtransients |