scholarly journals Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking

2014 ◽  
Vol 266 ◽  
pp. 1-16 ◽  
Author(s):  
A. Lázaro ◽  
L. Ammirabile ◽  
G. Bandini ◽  
G. Darmet ◽  
S. Massara ◽  
...  
2015 ◽  
Vol 98-99 ◽  
pp. 2235-2238 ◽  
Author(s):  
Massimo Zucchetti ◽  
Bruno Coppi ◽  
Maria Teresa Porfiri ◽  
Marco Riva

2011 ◽  
Vol 175 (2) ◽  
pp. 468-479 ◽  
Author(s):  
A. Moisseytsev ◽  
Y. Tang ◽  
S. Majumdar ◽  
C. Grandy ◽  
K. Natesan

2011 ◽  
Author(s):  
Juan Carbajo ◽  
Hae-Yong Jeong ◽  
Roald Wigeland ◽  
Michael Corradini ◽  
Rodney Cannon Schmidt ◽  
...  

2016 ◽  
pp. 9-12
Author(s):  
Yu. Vorobyov ◽  
A. Nosovsky ◽  
O. Pohonets ◽  
I. Shevchenko

The paper presents thermal-hydraulic analysis of mixed core loads to confirm compliance with safety criteria. The objective is to verify reliability of nuclear fuel cooling in representative events of the design-basis accident analysis. RELAP5/MOD3.2 computer code was applied to show that maximum fuel cladding temperature does not exceed 1200 °C in mixed TVSA-12, TVS-WR and TVSA cores. The analysis led to the conclusion on possible safe implementation of new fuel at Ukrainian NPPs.


2010 ◽  
pp. 2321-2710 ◽  
Author(s):  
Jacques Rouault ◽  
P. Chellapandi ◽  
Baldev Raj ◽  
Philippe Dufour ◽  
Christian Latge ◽  
...  

Author(s):  
Kenta Ichikawa ◽  
Hironori Kanda ◽  
Naoki Yoshioka ◽  
Kuniaki Ara ◽  
Jun-ichi Saito ◽  
...  

Studies on the suppression of the reactivity of sodium itself have been performed on the basis of the concept of suspended nanoparticles in liquid sodium (sodium nanofluid). According to the theoretical and experimental results of studies for sodium nanofluid, velocity and heat of sodium nanofluid reaction with water (sodium nanofluid/water reaction) are lower than those of the pure sodium/water reaction. The analytical model for the peak temperature of a sodium nanofluid/water reaction jet has been developed by the authors in consideration of these suppression effects. In this paper, the prediction method for mitigation effects on damage of adjacent tubes in steam generator tube rupture (SGTR) accidents is developed by applying this analytical model for the peak temperature of the reaction jet. On the assumption that the sodium nanofluid is used for the secondary coolant of sodium-cooled fast reactor (SFR), mitigation effects under the design basis accident (DBA) condition and the design extension condition (DEC) of SGTR are estimated by using this method. The results indicate a clear possibility to reduce the number of damaged tubes and to suppress the pressure generated in SGTR accidents by using sodium nanofluid as the secondary coolant.


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