scholarly journals Regulatory Technology Development Plan - Sodium Fast Reactor: Mechanistic Source Term – Trial Calculation

2016 ◽  
Author(s):  
David Grabaskas ◽  
◽  
Matthew Bucknor ◽  
James Jerden ◽  
Acacia J. Brunett ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Source Term ◽  
Technology Development ◽  
Development Plan ◽  
Sodium Fast Reactor ◽  
Term Trial

scholarly journals Regulatory Technology Development Plan Sodium Fast Reactor. Mechanistic Source Term Development

2015 ◽  
Author(s):  
David S. Grabaskas ◽  
Acacia Joann Brunett ◽  
Matthew D. Bucknor ◽  
James J. Sienicki ◽  
Tanju Sofu
Keyword(s):  
Fast Reactor ◽  
Source Term ◽  
Technology Development ◽  
Development Plan ◽  
Sodium Fast Reactor

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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