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Featured researches published by Sean Dunagan.


Reliability Engineering & System Safety | 2010

Development of a code-agnostic computational infrastructure for the dynamic generation of accident progression event trees

Benjamin Rutt; Kyle Metzroth; Aram Hakobyan; Tunc Aldemir; Richard Denning; Sean Dunagan; David Kunsman

Analysis of dynamic accident progression trees (ADAPT) is a mechanized procedure for the generation of accident progression event trees. Use of ADAPT substantially reduces the manual and computational effort for Level 2 probabilistic risk assessment (PRA) of nuclear power plants; reduces the likelihood of input errors; determines the order of events dynamically; and treats accidents in a phenomenology consistent manner. ADAPT is based on the concept of dynamic event trees which use explicit modeling of the deterministic dynamic processes that take place within the plant (through system simulation codes such as MELCOR, RELAP) for the modeling of stochastic system evolution. The computational infrastructure of ADAPT is presented, along with a prototype implementation of ADAPT using MELCOR for the PRA modeling of a station blackout in a pressurized water reactor. The computational infrastructure allows for flexibility in linking with different simulation codes, parallel processing of the scenarios under consideration, on-line scenario management (initiation as well as termination) and user-friendly graphical capabilities.


challenges of large applications in distributed environments | 2006

Distributed dynamic event tree generation for reliability and risk assessment

Benjamin Rutt; Aram Hakobyan; Kyle Metzroth; Tunc Aldemir; Richard Denning; Sean Dunagan; David Kunsman

Level 2 probabilistic risk assessments of nuclear plants (analysis of radionuclide release from containment) may require hundreds of runs of severe accident analysis codes such as MELCOR or RELAP/SCDAP to analyze possible sequences of events (scenarios) that may follow given initiating events. With the advances in computer architectures and ubiquitous networking, it is now possible to utilize multiple computing and storage resources for such computational experiments. This paper presents a system software infrastructure that supports execution and analysis of multiple dynamic event-tree simulations on distributed environments. The infrastructure allow for 1) the testing of event tree completeness, and, 2) the assessment and propagation of uncertainty on the plant state in the quantification of event trees


Archive | 2008

Development and application of the dynamic system doctor to nuclear reactor probabilistic risk assessments.

David Kunsman; Tunc Aldemir; Benjamin Rutt; Kyle Metzroth; Richard Denning; Aram Hakobyan; Sean Dunagan

This LDRD project has produced a tool that makes probabilistic risk assessments (PRAs) of nuclear reactors - analyses which are very resource intensive - more efficient. PRAs of nuclear reactors are being increasingly relied on by the United States Nuclear Regulatory Commission (U.S.N.R.C.) for licensing decisions for current and advanced reactors. Yet, PRAs are produced much as they were 20 years ago. The work here applied a modern systems analysis technique to the accident progression analysis portion of the PRA; the technique was a system-independent multi-task computer driver routine. Initially, the objective of the work was to fuse the accident progression event tree (APET) portion of a PRA to the dynamic system doctor (DSD) created by Ohio State University. Instead, during the initial efforts, it was found that the DSD could be linked directly to a detailed accident progression phenomenological simulation code - the type on which APET construction and analysis relies, albeit indirectly - and thereby directly create and analyze the APET. The expanded DSD computational architecture and infrastructure that was created during this effort is called ADAPT (Analysis of Dynamic Accident Progression Trees). ADAPT is a system software infrastructure that supports execution and analysis of multiple dynamic event-tree simulations on distributed environments. A simulator abstraction layer was developed, and a generic driver was implemented for executing simulators on a distributed environment. As a demonstration of the use of the methodological tool, ADAPT was applied to quantify the likelihood of competing accident progression pathways occurring for a particular accident scenario in a particular reactor type using MELCOR, an integrated severe accident analysis code developed at Sandia. (ADAPT was intentionally created with flexibility, however, and is not limited to interacting with only one code. With minor coding changes to input files, ADAPT can be linked to other such codes.) The results of this demonstration indicate that the approach can significantly reduce the resources required for Level 2 PRAs. From the phenomenological viewpoint, ADAPT can also treat the associated epistemic and aleatory uncertainties. This methodology can also be used for analyses of other complex systems. Any complex system can be analyzed using ADAPT if the workings of that system can be displayed as an event tree, there is a computer code that simulates how those events could progress, and that simulator code has switches to turn on and off system events, phenomena, etc. Using and applying ADAPT to particular problems is not human independent. While the human resources for the creation and analysis of the accident progression are significantly decreased, knowledgeable analysts are still necessary for a given project to apply ADAPT successfully. This research and development effort has met its original goals and then exceeded them.


Nuclear Engineering and Design | 2008

Dynamic generation of accident progression event trees

Aram Hakobyan; Tunc Aldemir; Richard Denning; Sean Dunagan; David Kunsman; Benjamin Rutt


Transactions of the american nuclear society | 2006

Treatment of uncertainties in modeling the failure of major RCS components in severe accident analysis.

David Kunsman; Tunc Aldemir; Richard Denning; Aram Hakobyan; Sean Dunagan


Archive | 2008

Prioritization of technical content and impact assessment for changes to performance assessment at the Waste Isolation Pilot Plant (WIPP).

Martin B. Nemer; Eric D. Vugrin; Sean Dunagan


Archive | 2007

Analysis Report for the Shielded Container Performance Assessment

Sean Dunagan; Gregory T. Roselle; Eric D. Vugrin; John S. Long


Transactions of the american nuclear society | 2006

Treatment of uncertainties in modeling hydrogen burning in the containment during severe accidents

Aram Hakobyan; Richard Denning; Tunc Aldemir; Sean Dunagan; David Kunsman


Archive | 2011

Reevaluating Transuranic Waste Characterization for the Waste Isolation Pilot Plant.

Daniel James Clayton; Sean Dunagan; Moo Y Lee


Archive | 2010

ADAPT (Analysis of Dynamic Accident Progression Trees) Beta Version 0.9

David Kunsman; Sean Dunagan

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David Kunsman

Sandia National Laboratories

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Moo Y Lee

Sandia National Laboratories

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