On the quantification of safety margins

Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004. === Includes bibliographical references (leaves 117-124). === The nuclear industry has relied on the concept of Defense in Depth (DID) and traditional safety margins to deal with the uncertainties associated...

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Main Author: Pagani, Lorenzo P
Other Authors: George E. Apostolakis.
Format: Others
Language:English
Published: Massachusetts Institute of Technology 2006
Subjects:
Online Access:http://hdl.handle.net/1721.1/33642
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spelling ndltd-MIT-oai-dspace.mit.edu-1721.1-336422019-05-02T15:51:05Z On the quantification of safety margins Pagani, Lorenzo P George E. Apostolakis. Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Nuclear Engineering. Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004. Includes bibliographical references (leaves 117-124). The nuclear industry has relied on the concept of Defense in Depth (DID) and traditional safety margins to deal with the uncertainties associated with the design and operation of nuclear facilities. These concepts were formulated in the early days of development of nuclear power when these uncertainties could not be quantified. The subsequent development of Probabilistic Risk Assessment (PRA) has provided the analytical tools that allow the quantification of uncertainties associated with accident initiation and progression. But, while the impact of redundancy has been explicitly modeled and quantified, the role of safety margins is still not explicitly taken into account. The present work identifies the impact of safety margins in the PRA and proposes a methodology to quantify them. Practical examples are developed and discussed in two case studies. In the first study, we analyze the passive cooling of a gas-cooled fast reactor and we use an importance sampling Monte Carlo technique to propagate the epistemic uncertainties and to calculate the overall probability of failure. A comparison with an alternative active design is considered also. The results show that the active system can have, for this particular application, better reliability than the passive one. (cont.) An approach to derive the uncertainty distribution on the capacity is presented in the second case study, where computer simulations are performed to propagate uncertainties and to derive a probabilistic failure limit for high burnup fuel in a PWR rod ejection accident. by Lorenzo P. Pagani. Ph.D. 2006-07-31T15:19:31Z 2006-07-31T15:19:31Z 2004 2004 Thesis http://hdl.handle.net/1721.1/33642 64394636 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 199 leaves 8476178 bytes 8484564 bytes application/pdf application/pdf application/pdf Massachusetts Institute of Technology
collection NDLTD
language English
format Others
sources NDLTD
topic Nuclear Engineering.
spellingShingle Nuclear Engineering.
Pagani, Lorenzo P
On the quantification of safety margins
description Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004. === Includes bibliographical references (leaves 117-124). === The nuclear industry has relied on the concept of Defense in Depth (DID) and traditional safety margins to deal with the uncertainties associated with the design and operation of nuclear facilities. These concepts were formulated in the early days of development of nuclear power when these uncertainties could not be quantified. The subsequent development of Probabilistic Risk Assessment (PRA) has provided the analytical tools that allow the quantification of uncertainties associated with accident initiation and progression. But, while the impact of redundancy has been explicitly modeled and quantified, the role of safety margins is still not explicitly taken into account. The present work identifies the impact of safety margins in the PRA and proposes a methodology to quantify them. Practical examples are developed and discussed in two case studies. In the first study, we analyze the passive cooling of a gas-cooled fast reactor and we use an importance sampling Monte Carlo technique to propagate the epistemic uncertainties and to calculate the overall probability of failure. A comparison with an alternative active design is considered also. The results show that the active system can have, for this particular application, better reliability than the passive one. === (cont.) An approach to derive the uncertainty distribution on the capacity is presented in the second case study, where computer simulations are performed to propagate uncertainties and to derive a probabilistic failure limit for high burnup fuel in a PWR rod ejection accident. === by Lorenzo P. Pagani. === Ph.D.
author2 George E. Apostolakis.
author_facet George E. Apostolakis.
Pagani, Lorenzo P
author Pagani, Lorenzo P
author_sort Pagani, Lorenzo P
title On the quantification of safety margins
title_short On the quantification of safety margins
title_full On the quantification of safety margins
title_fullStr On the quantification of safety margins
title_full_unstemmed On the quantification of safety margins
title_sort on the quantification of safety margins
publisher Massachusetts Institute of Technology
publishDate 2006
url http://hdl.handle.net/1721.1/33642
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