Sensitivity analysis of the accident rate of a plant equipped with a protection channel under aging by the generalized perturbation theory

Author:

de Souza L.F.A.,Teixeira D.G.,Frutuoso e Melo P.F.,da Silva F.C.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference38 articles.

1. NRC, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Regulatory Guide 1.174, Rev. 3, Nuclear Regulatory Commission, Washington, DC, 2018.

2. IAEA, Deterministic Safety Analysis for Nuclear Power Plants, Specific Safety Guide No. SSG-2 (Rev. 1, International Atomic Energy Agency, Vienna, 2019.

3. IAEA, Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants, Specific Safety Guide No. SSG-3, International Atomic Energy Agency, Vienna, 2010.

4. U.S. Government Publishing Office. Part 20 – Standards for protection against radiation. In: Report AE 2.106/3:10/ U.S. Code of Federal Regulations (annual edition), U.S. Government Publishing Office, 2016. Available at: https://www.govinfo.gov/app/details/CFR-2016-title10-vol1/CFR-2016-title10-vol1-part20/summary. Accessed Jun 2019.

5. Influence of the demand rate and repair rate on the reliability of a single-channel protective system“;Oliveira;Reliability Engineering,1987

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