Incorporating reliability analysis into the design of passive cooling systems with an application to a gas-cooled reactor

Nuclear Engineering and Design

Volumn 238, Issue 1, 2008, Pages 217-228

  Mackay, Francisco J ^a   Apostolakis, George E ^a   Hejzlar, Pavel ^a  

^a Massachusetts Institute of Technology Cambridge   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

GAS COOLED REACTORS; HEAT EXCHANGERS; HELIUM; MATHEMATICAL MODELS; PRESSURE DROP;

DECAY HEAT REMOVAL (DHR); HELIUM-COOLED FAST REACTOR; TIME-DEPENDENT RELIABILITY EVALUATION;

COOLING SYSTEMS;

EID: 37749030024     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2007.04.006     Document Type: Article

References (17)

1. ANS. American National Standard for Decay Heat Power in Light Water Reactors, ANSI/ANS-5.1-1979 (1979), American Nuclear Society, La Grange Park, Illinois
2. Apostolakis G.E. A commentary on model uncertainty. In: Mosleh A., Siu N., Smidts C., and Lui C. (Eds). Proceedings of Workshop on Model Uncertainty: Its Characterization and Quantification. Annapolis, MD, October 20-22, 1993, US Nuclear Regulatory Commission, Washington, DC (1994) Report NUREG/CP-0138
3. Burgazzi L. Reliability evaluation of passive systems through functional reliability assessment. Nucl. Technol. 144 (2003) 145-151
4. Burgazzi L. Evaluation of uncertainties related to passive systems performance. Nucl. Eng. Des. 230 (2004) 93-106
5. Delaney M.J., Apostolakis G.E., and Driscoll M.J. Risk-informed design guidance for future reactor systems. Nucl. Eng. Des. 235 (2005) 1537-1556
6. Ghosh S.T., and Apostolakis G.E. Extracting risk insights from performance assessments for high-level radioactive waste repositories. Nucl. Technol. 153 (2006) 70-88
7. Hejzlar, P., Kim, S.J., Williams, W.C., Transient ATHENA/RELAP5-3D Calculations for a 600MWth Plate-Type Helium GFR, MIT Report MIT-GFR-026, Massachusetts Institute of Technology, Cambridge, MA, 2005.
8. Helton J.C., and Davis J.F. Latin hypercube sampling and the propagation of uncertainty in analyses of complex systems. Reliab. Eng. Syst. Saf. 81 (2003) 23-69
9. Hornberger G.M., and Spear R.C. An approach to the preliminary analysis of environmental systems. J. Environ. Manage. 12 (1981) 7-18
10. IAEA. Safety Related Terms for Advanced Nuclear Power Plants, TEC-DOC-626 (1991), International Atomic Energy Agency, Vienna, Austria
11. © code manual volume I: code structure, system models, and solution methods, INEEL-EXT-98-00834. Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho.
12. Jafari J., D'Auria F., Kazeminejad H., and Davilu H. Reliability evaluation of a natural circulation system. Nucl. Eng. Des. 224 (2003) 79-104
13. Lee, J.I., Hejzlar, P., 2007. Experimental and computational analysis of gas natural circulation loop, Proceedings of the International Congress on Advances in Nuclear Power Plants ICAPP '07, Paper 7381, Nice, France, May 13-18.
14. Marquès M., Pignatel J.F., Saignes P., D'Auria F., Burgazzi L., Müller C., Bolado-Lavin R., Kirchsteiger C., La Lumia V., and Ivanov I. Methodology for the reliability evaluation of a passive system and its integration into a probabilistic safety assessment. Nucl. Eng. Des. 235 (2005) 2612-2631
15. Mizuno Y., Ninokata H., and Finnicum D.J. Risk-informed design of IRIS using a level-1 probabilistic risk assessment from its conceptual design phase. Reliab. Eng. Syst. Saf. 87 (2005) 201-209
16. Pagani L.P., Apostolakis G.E., and Hejzlar P. The impact of uncertainties on the performance of passive systems. Nucl. Technol. 149 (2005) 129-140
17. Zio E., Cantarella M., and Cammi A. The analytic hierarchy process as a systematic approach to the identification of important parameters for the reliability assessment of passive systems. Nucl. Eng. Des. 226 (2003) 311-336