Corrosion Behavior of Zirconium, Titanium, and Their Alloys in Simulated Dissolver Solution of Fast Breeder Reactor Spent Nuclear Fuel Using Zircaloy-4 Mock-Up Dissolver Vessel

2015 ◽  
Vol 191 (1) ◽  
pp. 58-70 ◽  
Author(s):  
J. Jayaraj ◽  
K. Thyagarajan ◽  
C. Mallika ◽  
U. Kamachi Mudali
2012 ◽  
Vol 1475 ◽  
Author(s):  
A. Loida ◽  
R. Gens ◽  
C. Bube ◽  
K. Lemmens ◽  
C. Cachoir ◽  
...  

ABSTRACTIn accordance with the Belgian “supercontainer design”, spent nuclear fuel (SNF) will be encapsulated in carbon steel canisters, surrounded by a concrete overpack for disposal in poorly-indurated clay. After re-saturation of the barriers by porewater, interactions with the concrete will result in solutions rich in NaOH, KOH and Ca(OH)2. Corrosion studies of SNF in ECW-type solution (Evolved Cement Water) and YCWCa-type solution (Young Cement Water with Ca) were performed under externally applied H2 overpressures over 426 days. Directly after H2 application, Tc concentrations decreased from >10-8 M to concentrations below detection limit. Based on the fractional release of selected fission products, low matrix dissolution rates of ~10-8/day were found in both experiments. U concentrations decreased finally to 1.5•10-9 M (YCWCa) and to 2.1•10-10 M (ECW), respectively. Am, Np and Pu concentrations were found throughout the experiments below their detection limits indicating an effective retention process.


2013 ◽  
Vol 52 (7) ◽  
pp. 3491-3509 ◽  
Author(s):  
Thomas Fanghänel ◽  
Vincenzo V. Rondinella ◽  
Jean-Paul Glatz ◽  
Thierry Wiss ◽  
Detlef H. Wegen ◽  
...  

2002 ◽  
Author(s):  
Glenn E. McCreery ◽  
Keith G. Condie ◽  
Randy C. Clarksean ◽  
Donald M. McEligot

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin

ANRI ◽  
2020 ◽  
pp. 45-53
Author(s):  
A. Lachugin ◽  
M. Kocherygin ◽  
A. Gayazov ◽  
Yury Martynyuk ◽  
A. Vasil'ev

The paper presents basic results of development of a criticality accident alarm system to ensure safe retrieval of the spent nuclear fuel from the Lepse Floating Maintenance Base. The key features and engineering aspects of the system design are described. Locations of criticality detector units and selected alarm level settings are justified, hazardous area boundaries were identified, and parameters to identify inadequately protected zones were calculated. The SRKS-01D criticality accident alarm system by SPC “Doza” was selected as base equipment. The system was commissioned in 2019 and has been successfully operated for more than 6 months.


2018 ◽  
Author(s):  
Kaushik Banerjee ◽  
Thomas M. Evans ◽  
Gregory G. Davidson ◽  
Steven P. Hamilton

2020 ◽  
Author(s):  
Benjamin Roach ◽  
Cole Hexel ◽  
Kayron Rogers ◽  
Jeffrey (Jeff) Delashmitt ◽  
Shalina Metzger ◽  
...  

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