scholarly journals Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.

2011 ◽  
Author(s):  
Juan Carbajo ◽  
Hae-Yong Jeong ◽  
Roald Wigeland ◽  
Michael Corradini ◽  
Rodney Cannon Schmidt ◽  
...  
Author(s):  
Joel Guidez ◽  
Janos Bodi ◽  
Konstantin Mikityuk ◽  
Enrico Girardi ◽  
Bernard Carluec

Abstract Following up the previous CP-ESFR project, the ESFR-SMART project considers the safety objectives envisaged for Generation-IV reactors, taking into account the lessons learned from the Fukushima accident, in order to increase the safety level of the European Sodium Fast Reactor (ESFR). In accordance with these objectives, guidelines have been defined to drive the ESFR-SMART developments, mainly simplifying the design and using all the positive features of Sodium Fast Reactors (SFR), such as low coolant pressure, efficiency of natural convection, possibility of decay heat removal (DHR) by atmospheric air, high thermal inertia and long grace period before a human intervention is needed. In this paper, a set of new ambitious safety measures is introduced for further evaluation within the project. The proposed set aims at consistency with the main lines of safety evolutions since the Fukushima accident, but it does not yet constitute the final comprehensive safety analysis. The paper gives a first review of the new propositions to enhance the ESFR safety, leading to a simplified reactor, forgiving and including a lot of passivity. This first version is supported by the various project tasks in order to assess the relevance of the whole design in comparison to the final safety objectives.


Author(s):  
K. Mikityuk ◽  
E. Girardi ◽  
J. Krepel ◽  
E. Bubelis ◽  
E. Fridman ◽  
...  

Author(s):  
Joel Guidez ◽  
Janos Bodi ◽  
Konstantin Mikityuk ◽  
Enrico Girardi ◽  
Jeremy Bittan ◽  
...  

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.


Author(s):  
Joel Guidez ◽  
Janos Bodi ◽  
Konstantin Mikityuk ◽  
Enrico Girardi

Abstract Based on feedback from existing reactors and current projects, the European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ESFR SMART) project proposes an optimization of the secondary circuit with the main aim of improving safety. Besides, the optimization also leads to a simplification of the circuits and therefore to a reduction of the cost of the reactor. For the implementation of the proposed new design option, some points require further R&D to validate their feasibility.


2012 ◽  
Author(s):  
Tanju Sofu ◽  
Jeffrey L. LaChance ◽  
R. Bari ◽  
Roald Wigeland ◽  
Matthew R. Denman ◽  
...  

1979 ◽  
Author(s):  
N.M. Greene ◽  
V.M. Forsberg ◽  
G.B. Raiford ◽  
J.W. Arwood ◽  
G.F. Flanagan

Author(s):  
Emil Fridman ◽  
Francisco Álvarez Velarde ◽  
Pablo Romojaro Otero ◽  
Haileyesus Tsige-Tamirat ◽  
Antonio Jiménez-Carrascosa ◽  
...  

Abstract In the framework of the Horizon 2020 project ESFR-SMART (2017-2021), the European Sodium Fast Reactor (ESFR) core was updated through a safety-related modification and optimization of the core design from the earlier FP7 CP-ESFR project (2009-2013). This study is dedicated to neutronic analyses of the improved ESFR core design. The conducted work is reported in two parts. Part I deals with the evaluation of the safety-related neutronic parameters of the fresh Beginning-of-Life (BOL) core carried out by 8 organizations using both continuous energy Monte Carlo and deterministic computer codes. In addition to the neutronics characterization of the core, a special emphasis was put on the calibration and verification of the computational tools involved in the analyses. Part II is devoted to once-through and realistic batch-wise burnup calculations aiming at the establishing of the equilibrium core state, which will later serve as a basis for detailed safety analyses.


1980 ◽  
Author(s):  
V.M. Forsberg ◽  
J.W. Arwood ◽  
N.M. Greene ◽  
G.B. Raiford

1979 ◽  
Author(s):  
N.M. Greene ◽  
V.M. Forsberg ◽  
G.B. Raiford ◽  
J.W. Arwood ◽  
D.B. Simpson ◽  
...  

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