Advanced sodium fast reactor accident source terms :

Unprotected loss of flow accident (ULOF) is the most typical severe accident in sodium cooled fast reactor, which is focused by scholars civil and abroad. Metallic fuel has different safety characteristics with the oxide fuel as the important development direction of future sodium fast reactor, accident analysis of which is also a research focus at home and abroad. This paper bases on one Cooperation Research Project proposed by ANL and organized by IAEA, analyses the Shut-down Removal Test-45R of the metallic fuel sodium cooled fast reactor EBR-II in the US with SAS4A code, to research the transient characteristics of it in ULOF accident. Studies have shown that, metallic fuel sodium cooled fast reactor has very good inherent safety performance, which can reduce the reactor power in ULOF accident through the negative feedback itself.

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Regulatory Technology Development Plan - Sodium Fast Reactor. Mechanistic Source Term - Metal Fuel Radionuclide Release

10.2172/1245176 ◽

2016 ◽

Cited By ~ 1

Author(s):

David Grabaskas ◽

Matthew Bucknor ◽

James Jerden

Keyword(s):

Fast Reactor ◽

Source Term ◽

Technology Development ◽

Development Plan ◽

Sodium Fast Reactor ◽

Metal Fuel ◽

Radionuclide Release

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

Progress in Nuclear Energy ◽

10.1016/j.pnucene.2021.103676 ◽

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

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

Annals of Nuclear Energy ◽

10.1016/j.anucene.2021.108600 ◽

2021 ◽

Vol 164 ◽

pp. 108600

Author(s):

Shibao Wang ◽

Konstantin Mikityuk ◽

Petrovic Dorde ◽

Dalin Zhang ◽

Guanghui Su ◽

...

Keyword(s):

Fast Reactor ◽

Sodium Fast Reactor

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Pressure waves in sodium during a fast reactor accident

Meccanica ◽

10.1007/bf02314744 ◽

1975 ◽

Vol 10 (2) ◽

pp. 78-86

Author(s):

Tullio Trombetti

Keyword(s):

Fast Reactor ◽

Pressure Waves ◽

Reactor Accident

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Decay Heat Characterization for the European Sodium Fast Reactor

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4051798 ◽

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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