Design of a hydrogen/tritium permeation sensor for Gen-IV sodium fast reactors

Vacuum ◽  
2021 ◽  
pp. 110414
Author(s):  
L. Candido ◽  
C. Alberghi ◽  
M. Utili
Author(s):  
Marie-Noe¨l Berton ◽  
Olivier Ancelet ◽  
Marie The´re`se Cabrillat ◽  
Ste´phane Chapuliot

The RCC-MR creep-fatigue rules were developed and written in the framework of studies for the first SFR (Sodium Fast Reactors). These reactors were characterized by low primary loads and moderately high temperatures. The rule thus has to be improved with the aim of decreasing its conservatisms in case of higher temperatures and/or higher pressures (for GEN IV Gas Cooled Reactors). Studies were realized to improve the rule on the following points: - the position of the temperature dwell time in the cycle : the current rule always considers that the dwell time is located at one of the extremes of the cycle, what can be very conservative in some cases, - the symmetrisation effect of the stabilized cycle, - the case where the primary loads vary during the cycle, - the primary and secondary stresses combination during the temperature dwell time for the evaluation of the stress relaxation. These works are based on viscoelastoplastic calculations of stabilized cycles and the new proposals are applied on different tests. The consequences on creep-fatigue damage evaluation can be very significant.


Energies ◽  
2017 ◽  
Vol 10 (12) ◽  
pp. 2079 ◽  
Author(s):  
Walter Borreani ◽  
Alessandro Alemberti ◽  
Guglielmo Lomonaco ◽  
Fabrizio Magugliani ◽  
Paolo Saracco
Keyword(s):  
Gen Iv ◽  

2011 ◽  
Vol 173 (2) ◽  
pp. 162-175 ◽  
Author(s):  
Matthew Memmott ◽  
Jacopo Buongiorno ◽  
Pavel Hejzlar

2019 ◽  
Vol 5 ◽  
pp. 1
Author(s):  
Alain Zaetta ◽  
Bruno Fontaine ◽  
Pierre Sciora ◽  
Romain Lavastre ◽  
Robert Jacqmin ◽  
...  

Generation-IV sodium fast reactors (SFR) will only become acceptable and accepted if they can safely prevent or accommodate reactivity insertion accidents that could lead to the release of large quantities of mechanical energy, in excess of the reactor containment's capacity. The CADOR approach based on reinforced Doppler reactivity feedback is shown to be an attractive means of effectively preventing such reactivity insertion accidents. The accrued Doppler feedback is achieved by combining two effects: (i) introducing a neutron moderator material in the core so as to soften the neutron spectrum; and (ii) lowering the fuel temperature in nominal conditions so as to increase the margin to fuel melting. This study shows that, by applying this CADOR approach to a Generation-IV oxide-fuelled SFR, the resulting core can be made inherently resistant to reactivity insertion accidents, while also having increased resistance to loss-of-coolant accidents. These preliminary results have to be confirmed and completed to meet multiple safety objectives. In particular, some margin gains have to be found to guarantee against the risk of sodium boiling during unprotected loss of supply power accidents. The main drawback of the CADOR concept is a drastically reduced core power density compared to conventional designs. This has a large impact on core size and other parameters.


2013 ◽  
Vol 91 (4) ◽  
pp. 640-648 ◽  
Author(s):  
Daniele Vivaldi ◽  
Frédéric Gruy ◽  
Nicole Simon ◽  
Christophe Perrais

2015 ◽  
Author(s):  
Baldev Raj ◽  
P. Chellapandi ◽  
P.R. Vasudeva Rao

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