Consideration of Uncertainties in Analyzing Nuclear Power Facilities’ Fire Hazard

Author:

Vorobyev Yu. B.,Urtenov D. S.,Karnaukhov V. E.,Podgornyi V. N.,Lukashenko M. L.

Publisher

Pleiades Publishing Ltd

Subject

Energy Engineering and Power Technology,Nuclear Energy and Engineering

Reference22 articles.

1. EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, EPRI 1011989, NUREG/CR-6850 (U. S. Nuclear Regulatory Commission. Office of Nuclear Reactor Research, Washington, DC, 2005), Vol. 1–2.

2. Y.-H. Lee, J.-H. Kim, and J.-E. Yang, “Application of the CFAST zone model to the Fire PSA,” Nucl. Eng. Des. 240, 3571–3576 (2010). https://doi.org/10.1016/j.nucengdes.2010.04.035

3. Fire Dynamics Tools (FDT): Quantitative Fire Hazard Analysis Methods for the U. S. Nuclear Regulatory Commission Fire Protection Inspection Program. Final Report, NUREG-1805 (U. S. Nuclear Regulatory Commission. Office of Nuclear Reactor Research, Washington, DC, 2004).

4. Nuclear Power Plant Fire Modeling Analysis Guidelines (NPP FIRE MAG). Final Report, NUREG-1934, EPRI 1023259 (U. S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Washington, DC, 2012).

5. V. D. Baibakov, Yu. B. Vorobyev, and V. D. Kuznetsov, Codes for Calculating Nuclear Reactors: Study Aid (Mosk. Energ. Inst., Moscow, 2003) [in Russian].

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