Effects of nonablation concrete outgassing on BWR Mark I debris/concrete interactions during severe accidents

Conference · Fri Jan 01 04:00:00 EST 1988 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5767577

Hyman, C R; Carroll, D E; Washington, K E

Two limitations in current corium-concrete interaction (CCI) modeling methodology have been recently identified as having a potentially larger impact on CCI calculations for the boiling water reactor (BWR) Mark I containment design. These limitations are extant in the CORCON module of the CONTAIN computer code. The calculations in this paper were performed with CONTAIN/OR, a variant of the released version of CONTAIN 1.1. The CONTAIN/OR code incorporates modifications to the CORCON/CONTAIN coupling at the corium/concrete interface and provides a new treatment of concrete degassing. The changes were developed to facilitate exploration of the MARK I corium spreading issue and to support Oak Ridge National Laboratory's scoping calculations for the task group on the BWR Mark I shell melt-through issue. It is assumed that mechanistic detail is not needed to capture the dominant effects of concrete degassing and that a simple release model, aimed at providing a first-order approximation of gas sources from heated concrete to the melt, will provide the capability to assess the importance of this effect. Interfaces were developed between this new model, the embedded version of CORCON in CONTAIN, and the other portions of the CONTAIN cavity model.

• Research Organization: Oak Ridge National Lab., TN (USA)
• OSTI ID: 5767577
• Report Number(s): CONF-881011-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 57
• Country of Publication: United States
• Language: English

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