scholarly journals Thorium-loaded low-power reactor installation operated with super-long fuel residence time

2016 ◽  
Vol 2 (3) ◽  
pp. 172-178
Author(s):  
I.V. Shamanin ◽  
S.V. Bedenko ◽  
Yu.B. Chertkov
2016 ◽  
Vol 2016 (2) ◽  
pp. 121-132 ◽  
Author(s):  
Igor’ Vladimirovich Shamanin ◽  
Sergej Vladimirovich Bedenko ◽  
Yurij Borisovich Chertkov

2010 ◽  
Vol 25 (3) ◽  
pp. 249-254 ◽  
Author(s):  
Tihomir Apostolov ◽  
Elka Anastasova ◽  
Valentin Anastassov

In 2001, the Bulgarian Government decided to refurbish and convert the research reactor in Sofia into a low-power reactor. Due to this, a partial dismantling of IRT-Sofia?s old systems and equipment was carried out with the intention of reusing the concrete bioshield in the construction of the new low-power research reactor. For a more efficient use of available resources, an engineering project known as ?The plan for the partial dismantling of IRT-Sofia equipment as a part of its refurbishment into a low-power research reactor? was drawn up and has since been successfully implemented.


1956 ◽  
Author(s):  
M. Treshow ◽  
E. Hamer ◽  
H. Pearlman ◽  
D. Rossin ◽  
D. Shaftman

2020 ◽  
Vol 129 ◽  
pp. 103492
Author(s):  
Ho Rim Moon ◽  
Deok Sung Han ◽  
Jae Gab Kim ◽  
Ji Yong Oh ◽  
Sang Won Lee ◽  
...  

Author(s):  
N. Reynier Tronche ◽  
C. Eysseric ◽  
JP. Dancausse

In November/December 2004, AREVA succeeded in reprocessing for the first time MOX spent fuels with a continuous dissolution process on the UP2-800 plant in La Hague. It was the industrial conclusion of preliminary and extensive studies realized by the CEA teams at the laboratory scale in Atalante facilities. The experiments were realized using MOx fuel obtained by MIMAS process and irradiated in Saint-Laurent des Eaux power reactor. The average burn-ups of the pin samples used for the studies were comprised between 28 GWd/T and 43 GWd/T. As the MOx fuel present a specific behavior versus dissolution due to the presence of PuO2 clusters, the solubility tests were mainly focused on the Pu behavior as a function of the temperature of dissolution (from 88 °C to boiling point) and the fuel burn-up. The fixed dissolution parameters were the residence time (8 hours), the initial acidity (near 8 M) and the sample size (35 mm). Available results concern dissolution kinetics, plutonium solubility and its distribution in the different flux (insoluble solids, solution).


1958 ◽  
Vol 1 (2) ◽  
pp. 135-140
Author(s):  
P. R. Bolton ◽  
E. C. Barnes ◽  
E. D. Durkosh ◽  
W. D. Small

1969 ◽  
Author(s):  
W. G. Homeyer
Keyword(s):  

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