MOX and UOX Fuel Melt Margin for European Pressurized Reactor

Patryk Oskar Stręciwilk , Adam Dominiak , Piotr Darnowski , Roman Domański

Abstract

Safety is of paramount importance inthe design and maintenanceof Nuclear Power Plants (NPP). The crucial area is the nuclear island,where irradiated elements are located. Fuel melt is a very dangerous possibility during serious incidents in the nuclear reactor core and could lead to the release of enormous amounts of ra- dioactive elements. Uranium Oxide (UOX) and Mixed Oxides (MOX) are currently being consideredas fuels for existing and planned NPPs. This paper addresses UOX and MOX fuel melt calculations using a prepared Thermal-Hydraulics (TH) model and reliable thermal conductivity of UOX and MOX fuel relations. This evaluation is performed for European Pressurized Reactor (EPR) geometry and thermophysical parameters.
Author Patryk Oskar Stręciwilk (FPAE / IHE)
Patryk Oskar Stręciwilk,,
- The Institute of Heat Engineering
, Adam Dominiak (FPAE / IHE)
Adam Dominiak,,
- The Institute of Heat Engineering
, Piotr Darnowski (FPAE / IHE)
Piotr Darnowski,,
- The Institute of Heat Engineering
, Roman Domański (FPAE / IHE)
Roman Domański,,
- The Institute of Heat Engineering
Journal seriesJournal of Power Technologies, ISSN 2083-4187
Issue year2013
Vol93
No3
Pages169-177
Keywords in EnglishFuel melt, Nuclear fuel, Thermal-hydraulics model
ASJC Classification2102 Energy Engineering and Power Technology
URL http://papers.itc.pw.edu.pl/index.php/JPT/article/view/434
Languageen angielski
File
434-2084-1-PB.pdf 773.48 KB
Score (nominal)12
Score sourcejournalList
ScoreMinisterial score = 10.0, 12-01-2020, ArticleFromJournal
Ministerial score (2013-2016) = 12.0, 12-01-2020, ArticleFromJournal
Publication indicators GS Citations = 2.0; Scopus SNIP (Source Normalised Impact per Paper): 2015 = 0
Citation count*2 (2020-08-29)
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