Probabilistic safety assessment in Canada

Reliability Engineering and System Safety

Volumn 62, Issue 1-2, 1998, Pages 33-42

  Zeng, Y ^a   Webster, P ^a   Hessel, P ^a  

^a Reliability and Risk Assess Section   (Canada)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; FAULT TREE ANALYSIS; MATHEMATICAL MODELS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; REGULATORY COMPLIANCE; RELIABILITY;

FAULT TREE MODELS; PROBABILISTIC SAFETY ASSESSMENT;

RISK ASSESSMENT;

EID: 0032182780     PISSN: 09518320     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0951-8320(98)00009-X     Document Type: Article

References (29)

1. Atomic Energy Control Act, R.S.C., 1985, c. A-16.
2. Nuclear Safety and Control Act, March 1997.
3. Lewis, W. B., The accident to the NRX reactor on December 12, 1952, AECL-232, 1953.
4. Hurst, D. G., The accident to the NRX reactor - Part II, AECL-233, 1953.
5. Siddall, E., Reactor safety standards and their attainment, CRNE-726, 1957.
6. Siddall, E. Statistical analysis of reactor safety standards. Nucleonics, 1959, 7(2), 64-69.
7. Laurence, G. C., Required safety in nuclear reactors, AECL-1923, 1961.
8. Laurence, G. C., Reliability requirements for nuclear power stations, AECB 1001, 1962.
9. Laurence, G. C., Probability considerations in reactor hazards appraisals, AECB 1016, 1966.
10. Hurst, G. G. and Boyd, F. C., Reactor licensing and safety requirements, AECB-1059, 1972.
11. Gumley, P., Safety design matrices (MDMS) as used in Canada for CANDU 600 MW Licensing, AECL Report, REP/CO-MISC-0068/1983.
12. Gumley, P., Use of fault tree/event tree sequence analysis in a safety review of CANDU plants, AECL-7373; also IAEA-CN-39/7, 1981.
13. Requirements for the safety analysis of CANDU Nuclear power plants, AECB consultative document C-6, June 1980.
14. Requirements for the safety analysis of CANDU nuclear power plants, AECB consultative document C-6 revision 1, October 1995. Draft.
15. Proposed quantitative approach to safety for nuclear power plants in Canada, ACNS-20, 1995.
16. Requirements for containment systems for CANDU nuclear plants, AECB regulatory document R-7, 1991.
17. Requirements for shutdown systems for CANDU nuclear plants, AECB regulatory document R-8, 1991.
18. Requirements for emergency core cooling systems for CANDU nuclear plants, AECB regulatory document R-9, 1991.
19. The use of two shutdown systems in reactors, AECB regulatory document R-10, 1977.
20. Reliability requirements for safety-related systems of nuclear reactor facilities, AECB C-98, revision 1 (draft), 1995.
21. Darlington probabilistic safety evaluation, Ontario Hydro, 1987.
22. Pickering NGS a risk assessment, Ontario Hydro, 1995.
23. King, F. K., Risk-based safety goals for Ontario hydro nuclear generation stations, Ontario Hydro report 89412, April 1990.
24. Heavy water plant probabilistic safety assessment, Ontario Hydro, 1993.
25. Allen, P. J. Summary of CANDU 6 probabilistic safety assessment study results. Nuclear Safety, 1990, 31(2), 202-214.
26. CANDU 3 conceptual probabilistic safety assessment, AECL, 1989.
27. Probabilistic safety assessment report, Wolson NPP 2/3/4, AECL, 1995.
28. CANDU 9 probabilistic safety assessment, AECL, 1996.
29. Pickering NGS a decay heat removal master plant logic diagram - phase II investigation, AECB research project 2.380.2, 1997.