Assessment study about the risk of Wilks’ formula for uncertainty quantification of design extension condition scenarios in prototype Gen-IV sodium fast reactor

2018 ◽  
Vol 55 (7) ◽  
pp. 746-755
Author(s):  
Sarah Kang ◽  
Jaeseok Heo ◽  
ChiWoong Choi ◽  
Kwi-Seok Ha ◽  
Sung Won Bae
Keyword(s):  
Uncertainty Quantification ◽  
Fast Reactor ◽  
Assessment Study ◽  
Sodium Fast Reactor ◽  
Gen Iv

scholarly journals New Reactor Safety Measures for the European Sodium Fast Reactor. Part II: Preliminary Assessment

2021 ◽  
Author(s):  
Joel Guidez ◽  
Janos Bodi ◽  
Konstantin Mikityuk ◽  
Enrico Girardi ◽  
Jeremy Bittan ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Heat Removal ◽  
Reactor Safety ◽  
Preliminary Assessment ◽  
Safety Measures ◽  
Decay Heat ◽  
European Project ◽  
Sodium Fast Reactor ◽  
Core Catcher ◽  
Gen Iv

Abstract The European project ESFR SMART offers innovative options of a sodium fast reactor to improve its safety. This paper explains the results of preliminary calculations made of the main options to verify the big lines of their feasibility. Design propositions and calculations are here provided of following innovative options: removal of the safety vessel, innovative decay heat removal systems, core catcher, thermal pumps and secondary loops. In conclusion, all these options seem able to fulfil the big lines of new safety rules for GEN-IV reactors. A status of the R&D necessary to validate these new options is also proposed.

Design and first operation of the MACARON irradiation experiment of Sodium Fast reactor absorber pins in the BOR-60 reactor

2021 ◽  
Vol 135 ◽  
pp. 103676
Author(s):  
T. Lambert ◽  
J.M. Escleine ◽  
B. Fontaine ◽  
S. Eremin ◽  
E. Muraleva ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Irradiation Experiment ◽  
Sodium Fast Reactor

Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13

2021 ◽  
Vol 164 ◽  
pp. 108600
Author(s):  
Shibao Wang ◽  
Konstantin Mikityuk ◽  
Petrovic Dorde ◽  
Dalin Zhang ◽  
Guanghui Su ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Sodium Fast Reactor

Decay Heat Characterization for the European Sodium Fast Reactor

2021 ◽  
Author(s):  
Antonio Jiménez-Carrascosa ◽  
Nuria Garcia Herranz ◽  
Jiri Krepel ◽  
Marat Margulis ◽  
Una Baker ◽  
...  
Keyword(s):  
Fast Reactor ◽  
State Of The Art ◽  
Nuclear Data ◽  
Summation Method ◽  
Heat Power ◽  
Coupled Transport ◽  
Decay Heat ◽  
Sodium Fast Reactor ◽  
Detailed Assessment ◽  
Commercial Size

Abstract In this work a detailed assessment of the decay heat power for the commercial-size European Sodium-cooled Fast Reactor (ESFR) at the end of its equilibrium cycle has been performed. The summation method has been used to compute very accurate spatial- and time-dependent decay heat by employing state-of-the-art coupled transport-depletion computational codes and nuclear data. This detailed map provides basic information for subsequent transient calculations of the ESFR. A comprehensive analysis of the decay heat has been carried out and interdependencies among decay heat and different parameters characterizing the core state prior to shutdown, such as discharge burnup or type of fuel material, have been identified. That analysis has served as a basis to develop analytic functions to reconstruct the spatial-dependent decay heat power for the ESFR for cooling times within the first day after shutdown.

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