Probabilistic Safety Assessment of ESBWR gravity driven cooling system

Aleksej Kaszko , Grzegorz Niewiński , Michał Stępień


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\textsubscript{LINE-A} line, the most important element are the basic events related in particular to the operation of service valves.
Author Aleksej Kaszko (FPAE / IHE)
Aleksej Kaszko,,
- The Institute of Heat Engineering
, Grzegorz Niewiński (FPAE / IHE)
Grzegorz Niewiński,,
- The Institute of Heat Engineering
, Michał Stępień (FPAE / IHE)
Michał Stępień,,
- The Institute of Heat Engineering
Journal seriesModern Engineering, ISSN 2450-5501
Issue year2020
Publication size in sheets0.3
Keywords in Englishnuclear power plant, Probabilistic Safety Assessment, PSA, Fault Tree Analysis, FTA, GraGravity Driven Cooling System, GDCS
Languageen angielski
Score (nominal)5
Score sourcejournalList
ScoreMinisterial score = 5.0, 03-07-2020, ArticleFromJournal
Citation count*
Share Share

Get link to the record

* presented citation count is obtained through Internet information analysis and it is close to the number calculated by the Publish or Perish system.
Are you sure?