Cobalt Spinel Catalyst for N2O Abatement in the Pilot Plant Operation–Long-Term Activity and Stability in Tail Gases

2014 ◽  
Vol 53 (25) ◽  
pp. 10335-10342 ◽  
Author(s):  
Marek Inger ◽  
Marcin Wilk ◽  
Magdalena Saramok ◽  
Gabriela Grzybek ◽  
Anna Grodzka ◽  
...  
Author(s):  
Jan Bárta ◽  
Lenka Procházková ◽  
Michaela Škodová ◽  
Kateřina Děcká ◽  
Xenie Popovič ◽  
...  

Based on our long term experience with the operation of a photochemical pilot plant, we propose an UV light-based technology for syntheses of nano-dimensional metal oxides (case study for ZnO,...


1994 ◽  
Vol 29 (10-11) ◽  
pp. 61-67 ◽  
Author(s):  
M. Fruhen ◽  
K. Böcker ◽  
S. Eidens ◽  
D. Haaf ◽  
M. Liebeskind ◽  
...  

The objective of this study is to investigate to what extent the nitrification capacity of a pilot-plant fixed-film reactor changes during extensive periods of nutrient supply deficiency. The examined pilot-plant was an upflow reactor filled with swelling clay of medium grain size (6 to 8 mm). The experiments revealed that the maximum nitrification rate remained practically constant during the first weeks after the onset of unregulated ammonium supply. The capacity declined slowly, dropping to approximately 66% of the initial capacity after about ten weeks. Still ammonium peaks of up to 8 mg/l were readily nitrified throughout the entire period of the experiment. The reduction in nitrification capacity during the observation period did not result from decay processes of biomass but from the reactor becoming blocked and thus hampering transfer processes. It could be observed that the detached organisms attached again further up. This semi-industrial project demonstrated that a plug-flow fixed-film reactor can be used as effective means of tertiary nitrification.


Author(s):  
Andreas Niebel ◽  
Axel Funke ◽  
Cornelius Pfitzer ◽  
Nicolaus Dahmen ◽  
Nicole Weih ◽  
...  

2004 ◽  
Vol 50 (10) ◽  
pp. 89-96 ◽  
Author(s):  
S. Puig ◽  
M.T. Vives ◽  
Ll. Corominas ◽  
M.D. Balaguer ◽  
J. Colprim

One of the problems of nitrogen removal from wastewater when applying sequencing batch reactor (SBR) technology, is the specific use of organic matter for denitrification purposes. Since easily biodegradable organic matter is rapidly consumed under aerobic or anoxic conditions (i.e. aerobic oxidation or anoxic denitrification, respectively), it is an important factor to consider when scaling up SBRs from the laboratory to real plant operation. In this paper, we present the results obtained in relation to scaling up reactors from lab-scale to pilot-plant scale, treating real wastewater from two different locations: the laboratory and in situ, respectively. In order to make using easily biodegradable organic matter more efficient, the filling phases of SBR cycles were adjusted according to a step-feed strategy composed of 6 anoxic-aerobic events. Feeding only occurred during anoxic phases. The results obtained demonstrated that the methodology may be useful in treating real wastewater with high carbon and nitrogen variations, as it always kept effluent levels lower than the official standards require (effluent total COD lower than 125 mg COD/L and effluent Total Nitrogen lower than 15 mg N/L).


2007 ◽  
Author(s):  
Malynda Jo Aragon ◽  
Randy L Everett ◽  
Malcolm Dean Siegel ◽  
Richard Joseph Kottenstette ◽  
William E Holub, Jr ◽  
...  

2010 ◽  
Vol 1265 ◽  
Author(s):  
Jean-Francois Lucchini ◽  
Hnin Khaing ◽  
Donald T. Reed

AbstractWhen present, uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant (WIPP), uranium is present in significant quantities, with about 647 metric tons to be placed in the repository [1]. Therefore, the chemistry of uranium, and especially its solubility, needs to be determined under WIPP-relevant conditions.Long-term experiments were performed to measure the solubility of uranium (VI) in carbonate-free ERDA-6 brine, a simulated WIPP brine, at pCH+ values between 8 and 12.5. These data, obtained from the over-saturation approach, were the first WIPP repository-relevant data for the VI actinide oxidation state. The solubility trends observed pointed towards low uranium solubility in WIPP brine and a lack of amphotericity. At the expected pCH+ in the WIPP (˜ 9.5), measured uranium solubility approached 10-7 M. The objective of these experiments was to establish a baseline solubility to further investigate the effects of carbonate complexation on uranium solubility in WIPP brines, during the ongoing research program in actinide solubility under WIPP-relevant conditions.


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