[1] U.S. Nuclear Regulatory Commission and Electric Power Research Institute, “EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Volume 2: Detailed Methodology”, NUREG/CR-6850 Supplement 1, EPRI 1008239, Technical Report, October 2004.
[2] Hossam Shalabi & George Hadjisophocleous, 2018 “CANDU Fire Database”, CNL Nuclear Review, 18 December 2018.
[3] Hossam Shalabi, 2016 “Fire Probabilistic Risk Assessment of Nuclear Reactors” Fire Engineering Page 80-86, 1 January 2016.
[4] Hossam Shalabi & George Hadjisophocleous, 2018 “CANDU Fire Probabilistic Risk Assessment (PRA) Model”, CNL Nuclear Review, 18 December 2018.
[5] CSA standard N293-95 “Fire Protection for CANDU Nuclear Power Plants”, February 1997.
[6] Hossam Shalabi & George Hadjisophocleous, 2019 “CANDU Fire Load Densities in Canadian Nuclear Plants paper”, CNL Nuclear Review, Accepted to be published.
[7] CSA standard N293-12 “Fire Protection for CANDU Nuclear Power Plants”, November 2017.
[8] NFPA (2016), ‘NFPA 557, Standard for Determination of Fire Load for Use in Structural Fire Protection Design’, National Fire Protection Association, Quincy MA.
[9] Thauvoye, C., Zhao, B., Klein, J., Fontana, M. (2009), ‘Fire Load Survey and Statistical Analysis’, Fire Safety Science, Vol. 9, pp 991-1002.
[10] Anon, P, (1942). ‘Building Materials and Science structures – Fire Resistance Classification of Building Construction’, Report of Subcommittee on Fire Resistance Classification of Central Housing Committee on Research, Design and Construction, Report BMS92, National Bureau of Standards, Washington.
[11] Green, M., (1977). ‘A Survey of Fire Loads in Modern Office Building – Some Preliminary Results’, Fire Technology, vol. 13(1), pp 42 – 52.
[12] Barnett, C. R., (1984). ‘‘Pilot Fire Load Survey,’’ Project Report No 3580, New Zealand Fire Protection Association. MacDonald Barnett Partners, Auckland.
[13] Yii, H. W., (2000). ‘Effects of Surface Area and Thickness on Fire Loads’, Fire Engineering Research report, No. 2000/13 University of Canterbury, Christchurch, New Zealand.
[14] NBCC. 2015. National Building Code of Canada 2015. National Research Council of Canada, Ottawa, Ontario.
[15] Hossam Shalabi & George Hadjisophocleous, 2019 “CANDU Fire PRA Qualitative Analysis Screening Step”, CNL Nuclear Review, Under Consideration
[16] Probabilistic set of filter criteria in the frame of Fire PSA, Florian Berchtold, Burkhard Forell, Ulrich Krause (2015) International Workshop on Fire Probabilistic Risk Assessment (PRA)
[17] Facharbeitskreis (FAK PSA) (2005a). Probabilistic Safety Analysis for Nuclear Power Plants: Methods for Probabilistic Safety Analysis for Nuclear Power Plants, Status: August 2005, BfS-SCHR-37/05, Salzgitter, October 2005.
[18] Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications Volume 7: Fire Dynamics Simulator (FDS), April 2007.
[19] IEEE 383-2015 - IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities.
[20] Inspection Manual Chapter 0609, Appendix F, “Fire Protection Significant Determination Process,” USNRC, February 2005 (available through the USNRC public website).