Integrated MELPROG/TRAC analyses of a PWR station blackout

Heames, T.J.; Smith, Ron

doi:10.1016/0029-5493(91)90076-t

Cited by 6 publications

(4 citation statements)

References 5 publications

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“…An IFCI input deck is similar to that specified by MELPROG'S Version 5.2 input description (Heames 1989). However, a number of extraneous parameters have been removed from the input and a number of additional quantities are required by the FCI models.…”

Section: Input and Outputmentioning

confidence: 97%

Integrated Fuel-Coolant Interaction (IFCI 7.0) Code User's Manual

Young¹

1999

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Section: Input and Outputmentioning

confidence: 97%

Integrated Fuel-Coolant Interaction (IFCI 7.0) Code User's Manual

Young¹

1999

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“…Core melt progression under the influence of natural circulation was modeled in the MELPROG code Heames and Smith, 1991) and in the SCDAP/RELAPS code (Bayless, 1988; Knudson and Dobbe, 1993;. In addition, the MELCOR code (Martinez et al, 1992) has been used to provide an independent assessment of the SCDAP/RELAPS results and to analyze full loop natural circulation scenarios not analyzed by SCDAP/RELAPS.…”

Section: Quantification Of Primary System Pressure and Temperaturementioning

confidence: 99%

“…PWRs, for example, we find no significant examples of departures from the crucible phenomenology found in TMI, while for BWRs, the gradual relocation scenario seems to be the norm (Hodge and Ott 1990;Kim et al, 1988). One notable exception is the MELPROG calculation by Heames and Smith (1989), in which molten cladding, and later fuel, was assumed to flow freely through the relatively large holes of the lower core plate. The particular calculation was for a station blackout with a pump seal LOCA.…”

Section: Bl Introductionmentioning

confidence: 99%

The probability of containment failure by direct containment heating in Zion

Pilch

Yan

Theofanous

1996

Nuclear Engineering and Design

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This report is the first step in the resolution of the Direct Containment Heating (DCH) issue for the Zion Nuclear Power Plant using the Risk Oriented Accident Analysis Methodology (ROAAM). This report includes the definition of a probabilistic framework that decomposes the DCH problem into three probability density functions that reflect the most uncertain initial conditions (UO, mass, zirconium oxidation fraction, and steel mass). Uncertainties in the initial

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“…Working group discussions pointed out that this scenario is overly conservative and that melting of upper plenum steel is strongly correlated with hot leg Mure. In fhct, gradual relocation has been predicted in only one MELPROG calculation for the Surry plant (Heames and Smith, 1987); and even here, hot leg Mure was predicted to occur before core relocation into the lower plenum. Should a gradual relocation occur, working group members believed that it would look like Scenario Vm at the time of vessel failure.…”

Section: Splinter Scenariosmentioning

confidence: 99%