The probability of containment failure by direct containment heating in Zion

Pilch, M.; Yan, Hongfei; Theofanous, T.G.

doi:10.1016/0029-5493(96)01227-7

Cited by 10 publications

(6 citation statements)

References 29 publications

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“…The initial size of such a failure is -0.025 meter (m), but melt flow through the hole will cause it to ablate to a much larger size. A final hole size of -0.4 m was computed with an ablation model (Pilch 1994~). The calculation was carried out using the melt mass (scaled to Surry, i.e., 43 metric tons (mtonnes)) and composition specified in the SASM document (Zuber et al 1991).…”

Section: Facility Geometrymentioning

confidence: 99%

Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant

Blanchat¹,

Pilch²,

Allen³

1997

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Section: Facility Geometrymentioning

confidence: 99%

Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant

Blanchat¹,

Pilch²,

Allen³

1997

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“…Spontaneous failure of the hot leg has been observed at these RCS pressures in more recent SCDAP/RELAP5 calculations for short-term station blackouts in Surry and Zion (Appendix C in Pilch et al 1994) if the hot leg is sufficiently hot. Mot leg failure in the long-term station blackout might also be expected because heating of the hot leg largely occurs during the Zr oxidation phase; however, STCP calculations cannot assess the likelihood of hot leg failure.…”

Section: F-2mentioning

confidence: 73%

The probability of containment failure by direct containment heating in surry

Pilch¹,

Allen²,

Bergeron³

et al. 1995

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“…Since early failure tends to have more severe consequences it is usually emphasized in APET analyses. Many mechanisms are present that can lead to early containment failure such as rapid overpressurization from severe accident phenomena such as direct containment heating that can result from reactor pressure vessel lower head failure with the primary system at high pressure [66,67] or explosive increase in pressure due to a steam explosion [68,69] or from hydrogen deflagration or detonation [70,71,72]. The main mechanism of late containment failure is through slow pressure buildup because of failure of AC-powered containment heat removal systems.…”

Section: Containment Overpressure Failurementioning

confidence: 99%

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

Kunsman¹,

Aldemir

Rutt

et al. 2008

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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.4

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The probability of containment failure by direct containment heating in Zion

Cited by 10 publications

References 29 publications

Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant

Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant

The probability of containment failure by direct containment heating in surry

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

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