Effect of void propagation to sodium void reactivity in transient analyses of fast reactors with sodium-plenum

2018 ◽  
Vol 119 ◽  
pp. 175-179 ◽  
Author(s):  
Toshikazu Takeda ◽  
Koji Fujimura ◽  
Kazuhiro Fujimata ◽  
Satoshi Takeda
2007 ◽  
pp. 48-62 ◽  
Author(s):  
L. Buiron ◽  
Ph. Dufour ◽  
G. Rimpault ◽  
G. Prulhiere ◽  
C. Thevenot ◽  
...  
Keyword(s):  

2019 ◽  
Vol 12 (4) ◽  
pp. 50-61
Author(s):  
А. Harutyunyan ◽  
S.B. Vygovskiy ◽  
A. Khachatryan

Atomic Energy ◽  
2021 ◽  
Author(s):  
N. V. Gorin ◽  
N. P. Voloshin ◽  
Yu. I. Churikov ◽  
A. N. Chebeskov ◽  
V. P. Kuchinov ◽  
...  

Energies ◽  
2021 ◽  
Vol 14 (15) ◽  
pp. 4610
Author(s):  
Ahmed Amin E. Abdelhameed ◽  
Chihyung Kim ◽  
Yonghee Kim

The floating absorber for safety at transient (FAST) was proposed as a solution for the positive coolant temperature coefficient in sodium-cooled fast reactors (SFRs). It is designed to insert negative reactivity in the case of coolant temperature rise or coolant voiding in an inherently passive way. The use of the original FAST design showed effectiveness in protecting the reactor core during some anticipated transients without scram (ATWS) events. However, oscillation behaviors of power due to refloating of the absorber module in FAST were observed during other ATWS events. In this paper, we propose an improved FAST device (iFAST), in which a constraint is imposed on the sinking (insertion) limit of the absorber module in FAST. This provides a simple and effective solution to the power oscillation problem. Here, we focus on an oxide fuel-loaded SFR that is characterized by a more negative Doppler reactivity coefficient and higher operating temperature than the metallic-loaded SFR cores. The study is carried out for the 1000 MWth advanced burner reactor with an oxide fuel-loaded core during postulated ATWS events that are unprotected transient over power, unprotected loss of flow, and unprotected loss of the heat sink. It was found that the iFAST device has promising potentials for protecting the oxide SFR core during the various studied ATWS events.


Author(s):  
C. W. Blumfield

SynopsisThe background to recent major advances in the construction and operation of fast reactors is outlined with particular reference to the Dounreay Prototype Fast Reactor. The advantages and disadvantages of sodium as a coolant of the high energy density assembly are discussed and an account given of the consequences of a leak and the precautions taken against this eventuality. Attention is drawn to the safety aspects of the system. The economics of the plans for fuel reprocessing are explained and an account given of the progress in the fabrication of fast reactor fuel pins. Finally the environmental impact of present and planned activities on the Dounreay site is presented in the context of participation in the European Collaboration on Fast Reactor Technology and attention drawn to the importance of the planning inquiry in progress at Dounreay.


Atomic Energy ◽  
2017 ◽  
Vol 122 (3) ◽  
pp. 178-184 ◽  
Author(s):  
E. V. Bogdanova ◽  
V. G. Zotov ◽  
S. A. Malkin ◽  
I. V. Vitkovskii ◽  
I. R. Kirillov ◽  
...  
Keyword(s):  

2017 ◽  
Vol 100 ◽  
pp. 103-113 ◽  
Author(s):  
Anne Baschwitz ◽  
Gilles Mathonnière ◽  
Sophie Gabriel ◽  
Jean-Guy Devezeaux de Lavergne ◽  
Yann Pincé

Nature ◽  
1968 ◽  
Vol 219 (5150) ◽  
pp. 203-203 ◽  
Author(s):  
J. WALKER
Keyword(s):  

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