IRIS Simplified LERF Model
Westinghouse is currently conducting the pre-application licensing of the International Reactor Innovative and Secure (IRIS). One of the key aspects of the IRIS design is its safety-by-designTM philosophy and within this framework the PRA is being used as an integral part of the design process. The most ambitious risk-related goal for IRIS is to reduce the Emergency Planning Zone (EPZ) to within the exclusion area by demonstrating that the off-site doses are consistent with the US Protective Action Guidelines (PAGs) for initiation of emergency response so that the required protective actions would be limited to the exclusion area. As a first step, a model has been developed to provide a first order approximation of the Large Early Release Frequency (LERF) as a surrogate predictor of the off-site doses. A key-aspect of the LERF model development is the characterization of the possible paths of release. Four main categories have been historically pointed out: (1) Core Damage (CD ) sequences with containment bypass, (2) CD sequences with containment isolation failure, (3) CD sequences with containment failure at low pressure and (4) CD sequences with containment failure at high pressure. They have been reevaluated to account for the IRIS design features.
- Research Organization:
- Polytechnic of Milan: via Ponzio, 34/3, 20133 Milano (IT); Westinghouse Electric Co., Windsor, CT (US); Tokyo Institute of Technology: 2-12-1 O-okayama, Meguro-ku, Tokyo (JP)
- Sponsoring Organization:
- none (US)
- OSTI ID:
- 841453
- Resource Relation:
- Conference: Americas Nuclear Energy Symposium (ANES 2004), Miami, FL (US), 10/03/2004--10/06/2004; Other Information: PBD: 6 Oct 2004
- Country of Publication:
- United States
- Language:
- English
Similar Records
MACCS1.5; Reactor Accident Consequence Code
MACCS1.5; Reactor Accident Consequence Code