Chemical interaction between uranium dioxide, boron carbide and stainless steel at 1900 °C — Application to a severe accident scenario in sodium cooled fast reactors

2021 ◽  
Vol 557 ◽  
pp. 153266
Author(s):  
Mathieu Garrigue ◽  
Andrea Quaini ◽  
Thierry Alpettaz ◽  
Christophe Bonnet ◽  
Emmanuelle Brackx ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Boron Carbide ◽  
Uranium Dioxide ◽  
Chemical Interaction ◽  
Severe Accident ◽  
Fast Reactors ◽  
Accident Scenario

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State

2020 ◽  
Author(s):  
Toshihide Takai ◽  
Tomohiro Furukawa ◽  
Hidemasa Yamano
Keyword(s):  
Stainless Steel ◽  
Solid State ◽  
Boron Carbide ◽  
Specific Heat ◽  
Thermophysical Properties ◽  
Crystalline Phase ◽  
Eutectic Mixture ◽  
Severe Accident ◽  
Eutectic Melting ◽  
Control Rod

Abstract In a core disruptive accident scenario, boron carbide, which is used as control rod material, may melt below the melting temperature of stainless steel due to the eutectic reaction with it. Produced eutectic mixture is assumed to relocate widely in the degraded core, and this behavior plays an important role to reduce the neutronic reactivity of the degraded core materials significantly. However, these behaviors have never been simulated in the severe accident computer codes, and reducing the uncertainty is important for reasonable assessment. To contribute improvement of the core disruptive accident analysis code to handle these eutectic melting and relocation behavior, authors had been carried out the evaluation of the thermophysical properties of stainless steel containing boron carbide, which needed as a basic data for cord improvement. Since the solubility range of boron against iron is expected to be wide, the crystalline phase of eutectic mixture may change according to boron concentration in the eutectic mixture. And this may affect the thermophysical properties themselves. In this work, the density and specific heat of stainless steel containing 17 mass% boron carbide in a solid state are obtained and compared with these of stainless steel containing 0 and 5 mass% boron carbide. By adding 17 mass boron carbide to stainless steel type 316L, the density decreased approximately 24% and the specific heat increased approximately 25% at 293 K. The density of stainless steel containing boron carbide tended to decrease almost linearly depending on the amount of boron carbide added, none the less for difference of crystalline phase. On the other hand, increasing trend of the specific heat of stainless steel containing 17 mass% boron carbide accompanying elevating temperature showed different behavior from that of stainless steel containing 0 and 5 mass% boron carbide. This difference in the trend of the specific heat was considered to be caused the difference in the crystalline phase.

Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident

2021 ◽  
pp. 1-14
Author(s):  
Ayumi Itoh ◽  
Nathan C. Andrews ◽  
David L. Luxat ◽  
Randall O. Gauntt ◽  
Masaki Kurata ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Degradation Mechanism ◽  
Severe Accident ◽  
Molten Mixture

scholarly journals Numerical investigations of stainless steel melt motions on the surface of uranium dioxide

2019 ◽  
Vol 196 ◽  
pp. 00005 ◽  
Author(s):  
Eduard V. Usov ◽  
Pavel D. Lobanov ◽  
Ilya A. Klimonov ◽  
Alexander E. Kutlimetov ◽  
Anton A. Butov ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Uranium Dioxide ◽  
Momentum Conservation ◽  
Mass Energy ◽  
Numerical Investigations ◽  
Fuel Rod ◽  
The Core ◽  
Fuel Pin ◽  
Energy And Momentum ◽  
Coolant Velocity

The paper contains the results of numerical simulation of stainless steel melt motions on the surface of uranium dioxide. The investigations are performed for purposes of understanding of the fuel rod behavior during the core disruptive accident in the fast reactors. The systems of mass, energy and momentum conservation equations are solved to simulate melt motion on the surface of the fuel pin. Heat transfer and friction between melt and pin's surface and melt and coolant flow are taken into consideration. The dependences of mass of the melt and the features of the melt motion on coolant velocity and contact angle between melt and surface of the fuel rod are presented.

Core to surge-line energy transport in a severe accident scenario

1995 ◽  
Vol 154 (2) ◽  
pp. 119-132 ◽  
Author(s):  
M. di Marzo ◽  
K. Almenas ◽  
S. Gopalnarayanan
Keyword(s):  
Energy Transport ◽  
Severe Accident ◽  
Line Energy ◽  
Accident Scenario ◽  
Surge Line

Simulation of the small modular reactor severe accident scenario response to SBO using MELCOR code

2016 ◽  
Vol 86 ◽  
pp. 87-96 ◽  
Author(s):  
Shasha Yin ◽  
Yapei Zhang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
G.H. Su ◽  
...  
Keyword(s):  
Severe Accident ◽  
Accident Scenario ◽  
Small Modular Reactor

Nitrogen Enhanced 316LN Austenitic Stainless Steel for Sodium Cooled Fast Reactors

2013 ◽  
Vol 794 ◽  
pp. 670-680 ◽  
Author(s):  
Tammana Jayakumar ◽  
A.K. Bhaduri ◽  
M.D. Mathew ◽  
Shaju K. Albert ◽  
U. Kamachi Mudali
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Weld Metal ◽  
Nitrogen Content ◽  
Low Cycle Fatigue ◽  
Hot Cracking ◽  
Cycle Fatigue ◽  
Fast Reactors ◽  
Delta Ferrite ◽  
316Ln Ss

For the future sodium-cooled fast reactors (SFRs), which are envisaged with a design life of 60 years, nitrogen-enhanced 316LN austenitic stainless steel (SS) with improved high-temperature properties is being developed. To optimize the enhanced nitrogen content in 316LN SS, the effect of nitrogen on its tensile, creep and low cycle fatigue behavior has been investigated. For different heats of 316LN SS containing 0.07-0.22 wt% nitrogen, the tensile and creep properties increased with increase in nitrogen content, while low cycle fatigue properties peaked at 0.14 wt% nitrogen. Finally, based on the evaluation of the hot cracking susceptibility of the different heats of 316LN SS with varying nitrogen content, using the Varestraint and Gleeble hot-ductility tests, the nitrogen content for the nitrogen-enhanced 316LN SS has been optimized at a level of 0.14 wt%. The 0.14 wt% nitrogen content in this optimised composition shifts the solidification mode of the weld metal to fully austenitic region, including that due to dilution of nitrogen from the base metal, thereby increasing its hot cracking susceptibility. This necessitated development and qualification of welding electrodes for obtaining weld metal with 0.14 wt% nitrogen by optimising the weld metal chemistry so as to obtain the requisite delta ferrite content, tensile properties, and very importantly impact toughness both in the as-welded and aged conditions. Studies on localised corrosion behaviour of nitrogen-enhanced 316LN SS indicated the beneficial effect of nitrogen addition to sensitization, pitting, intergranular corrosion, stress corrosion cracking and corrosion fatigue.

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