A Methodology for Grouping Source Terms for Consequence Calculations in Probabilistic Risk Assessments

Abstract

The individual plant analyses in the U.S. Nuclear Regulatory Commission's reassessment of the risk from commercial nuclear power plants (NUREG-1 150) consist of four parts: systems analysis, accident-progression analysis, source-term analysis, and consequence analysis. Careful definition of the interfaces between these parts is necessary for both information flow and computational efficiency. This paper describes the procedure used to define the interface between the sourceterm analysis and the consequence analysis. This interface is accomplished by forming groups of source terms with similar properties and then performing one set of MACCS calculations for each group.

Methods and models in process safety and risk management: Past, present and future

“…Probabilistic risk assessment performed as a part of NUREG-1150 consists of four major elements: system analysis, accident progression analysis, source-term analysis, and consequences analysis. Iman et al (1990) described the background of NUREG-1150 development and a procedure to define the interface between the source-term and the consequences analysis. Further, the uncertainty analysis associated with NUREG-1150 PRA was performed using Monte Carlo simulation based on Latin hypercube sampling (Imanl & Helton, 1991).…”