Probabilistic Safety Assessment of ESBWR gravity driven cooling system

• Autorzy: Kaszko Aleksej , Niewiński Grzegorz , Stępień Michał
• Języki publikacji: EN

Abstrakty

EN

According to Polish nuclear law, newly emerging nuclear facilities require probabilistic safety assessment (PSA). This article is intended to present the PSA method and to present the error tree method by which the probability of unavailability of the gravity reactor cooling system (GDCS) of the ESBWR power plant designed by GE Hitachi was determined. This work includes creatiion process of a damage tree and performing a quantitative analysis in SAPHIRE tool and estimating uncertainty using the Monte Carlo method. As a part of the work, it was shown that in the probability of failure of a single GDCS P LINE-A line, the most important element are the basic events related in particular to the operation of service valves.

Słowa kluczowe

EN

nuclear power plant; Probabilistic Safety Assessment; PSA; Fault Tree Analysis; FTA; Gravity Driven Cooling System; GDCS

• Wydawca: Centrum Rzeczoznawstwa Budowlanego Sp. z o.o.
• Czasopismo: Modern Engineering
• Rocznik: 2020
• Tom: 1
• Strony: 18--25
• Opis fizyczny: Bibliogr. 23 poz., rys.

Twórcy

autor

Kaszko Aleksej

• Institute of Heat Engineering, Warsaw University of Technology, Poland

autor

Niewiński Grzegorz

• Institute of Heat Engineering, Warsaw University of Technology, Poland

autor

Stępień Michał

• Institute of Heat Engineering, Warsaw University of Technology, Poland

Bibliografia

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Uwagi

PL

Opracowanie rekordu ze środków MNiSW, umowa Nr 461252 w ramach programu "Społeczna odpowiedzialność nauki" - moduł: Popularyzacja nauki i promocja sportu (2020).