The EBR-II probabilistic risk assessment: Lessons learned regarding passive safety

Reliability Engineering and System Safety

Volumn 62, Issue 1-2, 1998, Pages 43-50

  Hill, D J ^a   Ragland, W A ^a   Roglans, J ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; DECISION MAKING; LOSS OF COOLANT ACCIDENTS; NUCLEAR INDUSTRY; NUCLEAR REACTORS; REACTOR SHUTDOWNS; RELIABILITY; RISK MANAGEMENT;

PROBABILISTIC RISK ASSESSMENT; REACTOR SHUTDOWN SYSTEMS;

RISK ASSESSMENT;

EID: 0032183611     PISSN: 09518320     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0951-8320(97)00169-5     Document Type: Article

References (9)

1. Hill, D. J., Ragland, W. A. & Roglans, J., Experimental Breeder Reactor II (EBR-II) Level 1 Probabilistic Risk Assessment. Internal document, Argonne National Laboratory, Argonne, Illinois, 1991.
2. Planchon, H. P., Singer, R. M., Mohr, D., Feldman, E. E., Chang, L. K. & Betten P. R., The Experimental Breeder Reactor II inherent shutdown and heat removal tests - results and analysis. Nucl. Engrg. Des., 1986, 91, 287-296.
3. Draft Preapplication Safety Evaluation Report (SER) for the Power Reactor Inherently Safe Module Liquid Metal Reactor. Report NUREG-1368, USNRC, Washington, D.C., 1989.
4. Eide, S. A., Henry, D. M. & Thatcher, T. A., Advanced test reactor Level 1 Probabilistic Risk Assessment. In Proc. of the ANS Conference on The Safety, Status and Future of Noncommercial Reactors and Irradiation Facilities, Boise, Idaho, September 31-October 4, 1990.
5. Chu, T. L., Azarm, M. A., Bari, R., Lehner, J. & Luckas, W., Quantification of the Probabilistic Risk Assessment (PRA) of the Higher Flux Beam Reactor (HFBR) at Brookhaven National Laboratory. In Proc. of the ANS Conference on The Safety, Status and Future of Noncommercial Reactors and Irradiation Facilities, Boise, Idaho, September 31-October 4, 1990.
6. Flanagan, G. F., The use of PRA in management of safety issues at the high flux isotope reactor. In Proc. of the ANS Conference on The Safety, Status and Future of Noncommercial Reactors and Irradiation Facilities, Boise, Idaho, September 31-October 4, 1990.
7. Wyss, G. D., Kunsman, D. M. & Camp, A. L., Results and insights from the N Reactor Level II/III PRA for application to advanced reactor design. In Proc. of the ANS Conference on The Safety, Status and Future of Noncommercial Reactors and Irradiation Facilities, Boise, Idaho, September 31-October 4, 1990.
8. Tinnes, S. P., Cramer, D. S., Logan, V. E., Topp, S. V., Smith, J. A. & Brandyberry, M. D., Results of the Level 1 Probabilistic Risk Assessment (PRA) of internal events for heavy water production reactors (U). In Proc. of the ANS Conference on The Safety, Status and Future of Noncommercial Reactors and Irradiation Facilities, Boise, Idaho, September 31-October 4, 1990.
9. Brandyberry, M. D. & Wingo, H. E., External events analysis for the Savannah River Site K Reactor (U). In Proc. of the ANS Conference on The Safety, Status and Future of Noncommercial Reactors and Irradiation Facilities, Boise, Idaho, September 31-October 4, 1990.