IRIS pre-application licensing

Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy

Volumn , Issue , 2003, Pages 583-589

  Carelli, Mario D ^a   Kling, Charles L ^a   Ritterbusch, Stanley E ^a  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

Author keywords

IRIS; Passive safety systems; Probabilistic risk assessment; Risk informed; Safety by design

Indexed keywords

BOILING WATER REACTORS; NUCLEAR FUELS; NUCLEAR MATERIALS SAFEGUARDS; NUCLEAR REACTORS; PRESSURIZED WATER REACTORS; PROBABILITY; RISK ASSESSMENT; SECURITY SYSTEMS;

INTERNATIONAL REACTOR INNOVATIVE AND SECURE (IRIS); PASSIVE SAFETY SYSTEMS; PROBABILISTIC RISK ASSESSMENT; RISK-INFORMED; SAFETY-BY-DESIGN;

NUCLEAR REACTOR LICENSING;

EID: 2642518920     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (14)

1. Carelli, M. D., et al, "IRIS Reactor Conceptual Design," Intl. Conf. on the Back-End of the Fuel Cycle (Global 2001), Paris, France, September 9-13, 2001.
2. Carelli, M. D., et al., "The Design and Safety Features of the IRIS Reactor," ICONE11-36564, April 20-23, 2003.
3. Collado, J. M., "Design of the Reactor Pressure Vessel and Internals of the IRIS Integrated Nuclear System," ICAPP '03 3059, May 4-7, 2003.
4. Carelli, M. D., et al., "Safety by Design: A New Approach to Accident Management in the IRIS Reactor," IAEA-SR-218/36, IAEA Intl. Seminar on Status and Prospects of Small and Medium Sized Reactors, Cairo, Egypt, 27-31 May, 2001.
5. "IRIS Plant Description Document, " WCAP-16062-P and NP, March 21, 2003.
6. "Preliminary IRIS Safely Assessment," WCAP-16082-P and -NP, June 30, 2003.
7. "IRIS Phenomena Identification and Ranking Table (PIRT)", to be issued.
8. Staudenmeier, J., "Draft Regulatory Guide DG-1120 Transient and Accident Analysis Methods," USNRC, June 2002.
9. "IRIS Scaling Analysis," WCAP-16103-P and NP, April 24, 2003.
10. Zuber, N., "Appendix D: A Hierarchical, Two-Tired Scaling Analysis," An Integrated Structure and Scaling Methodology for Severe Accident Technical Issue Resolution, U.S. Nuclear Regulatory Commission, Washington, DC 20555, NUREG/CR-5809, November 1991.
11. USNRC REGULATORY GUIDE 1.174, "An Approach for Using Probabilistic Risk Assessment In Risk-informed Decisions on Plant-Specific Changes to the Licensing Basis," July 1998.
12. USNRC Draft Regulatory Guide DG-1110 (Proposed Revision 1 of Regulatory Guide 1.174), "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," June, 2001.
13. Travers, W. D., "Update of the Risk-Informed Regulation Implementation Plan," SECY-03-0044, March 21, 2003.
14. "A Risk-Informed, Performance-Based Regulatory Framework for Power Reactors," Nuclear Energy Institute, NEI 0202, May 2002.