Computer codes, severe accident consequences

Simultaneously with the design events analyses, considerable work was done to study the severe accidents consequences. Models were created and computer codes were verified. Analyses of different events were performed. 

Papazoglou, I. A. et al., 1992, On the Management of Severe Chemical Accidents DECARA A Computer code for Consequence Analysis in Chemical Installations Case Study September 14, 1998 Ammonia Plant, J. Haz. Mat. 31, pp 135-153. 

Release of radionuclides into the atmosphere is the main concern in the event of a nuclear reactor accident. The consequences of a severe reactor accident depend on the quantity, characteristics, and timing of the release of radionuclides from the reactor coolant system (RCS) into the containment, and finally into the atmosphere. The physical processes that influence the quantity and timing of a release are thought to be highly complex. In order to be able to predict the outcome of a nuclear accident. It is necessary to accurately model as many of the relevant physical processes as possible. VICTORIA-92 [1] is a mechanistic computer code designed to model such releases from the RCS during a severe reactor accident. 

NAS recommended that "the Department of Energy should commit to a significant program of severe accident model development and validation." The restart criteria define the scope of applicability of the criteria to three safety programs and their associated codes Technical Specifications, SAR, and PRA. The computational tools developed in the Severe Accident Assessment Program (SAAP) are used in PRA consequence analyses therefore, the validation of these codes is covered implicitly in the "Software Verification and Validation" section of this SER. 

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