Limited modifications of soya proteins by immobilized subtilisin: Comparison of products from different reactor types

1988 ◽  
Vol 32 (4) ◽  
pp. 475-481 ◽  
Author(s):  
A. B. Herbert ◽  
P. Dunnill
Keyword(s):  
Reactor Types ◽  
Soya Proteins ◽  
Immobilized Subtilisin

Fuel Cycle Incentives for Market Introduction of New Reactor Types in Europe

2006 ◽  
pp. 63-66
Author(s):  
Aliki Van Heek ◽  
Frodo Klaassen ◽  
Frederic Blom
Keyword(s):  
Fuel Cycle ◽  
Reactor Types

ASTEC: An Integral Code for Simulation of Severe Light Water Reactor Accidents

2006 ◽  
Author(s):  
N. Reinke ◽  
K. Neu ◽  
H.-J. Allelein
Keyword(s):  
Fission Products ◽  
Feasibility Studies ◽  
Current Status ◽  
Light Water ◽  
Fast Running ◽  
Severe Accidents ◽  
Loss Of Coolant Accident ◽  
Station Blackout ◽  
Water Reactors ◽  
Reactor Types

The integral code ASTEC (Accident Source Term Evaluation Code) commonly developed by IRSN and GRS is a fast running programme, which allows the calculation of entire sequences of severe accidents (SA) in light water reactors from the initiating event up to the release of fission products into the environment, thereby covering all important in-vessel and containment phenomena. Thus, the main fields of ASTEC application are intended to be accident sequence studies, uncertainty and sensitivity studies, probabilistic safety analysis level 2 studies as well as support to experiments. The modular structure of ASTEC allows running each module independently and separately, e.g. for separate effects analyses, as well as a combination of multiple modules for coupled effects testing and integral analyses. Among activities concentrating on the validation of individual ASTEC modules describing specific phenomena, the applicability to reactor cases marks an important step in the development of the code. Feasibility studies on plant applications have been performed for several reactor types such as the German Konvoi PWR 1300, the French PWR 900, and the Russian VVER-1000 and −440 with sequences like station blackout, small- or medium-break loss-of-coolant accident, and loss-of-feedwater transients. Subject of this paper is a short overview on the ASTEC code system and its current status with view to the application to severe accidents sequences at several PWRs, exemplified by selected calculations.

Use of γ-irradiation to produce films from whey, casein and soya proteins: structure and functionals characteristics

2002 ◽  
Vol 63 (3-6) ◽  
pp. 827-832 ◽  
Author(s):  
M Lacroix ◽  
T.C Le ◽  
B Ouattara ◽  
H Yu ◽  
M Letendre ◽  
...  
Keyword(s):  
Γ Irradiation ◽  
Soya Proteins

Biocatalytic properties of native and immobilized subtilisin 72 in aqueous-organic and low water media

2005 ◽  
Vol 32 (5-6) ◽  
pp. 253-260 ◽  
Author(s):  
Anna V. Bacheva ◽  
Anastasiya V. Belyaeva ◽  
Elena N. Lysogorskaya ◽  
Elena S. Oksenoit ◽  
Vladimir I. Lozinsky ◽  
...  
Keyword(s):  
Water Media ◽  
Immobilized Subtilisin

scholarly journals Investigation of Corrosion Resistance of Alloys with Potential Application in Supercritical Water-cooled Nuclear Reactors

2019 ◽  
Vol 63 (2) ◽  
pp. 328-332 ◽  
Author(s):  
Ákos Horváth ◽  
Attila R. Imre ◽  
György Jákli
Keyword(s):  
Corrosion Resistance ◽  
Supercritical Water ◽  
Power Plants ◽  
Fuel Cladding ◽  
Pressurized Water ◽  
Water Reactors ◽  
Reactor Types ◽  
Materials Used ◽  
Supercritical Water Cooled Reactor ◽  
Nuclear Applications

The Supercritical Water Cooled Reactor (SCWR) is one of the Generation IV reactor types, which has improved safety and economics, compared to the present fleet of pressurized water reactors. For nuclear applications, most of the traditional materials used for power plants are not applicable, therefore new types of materials have to be developed. For this purpose corrosion tests were designed and performed in a supercritical pressure autoclave in order to get data for the design of an in-pile high temperature and high-pressure corrosion loop. Here, we are presenting some results, related to corrosion resistance of some potential structural and fuel cladding materials.

scholarly journals Microbiological, histological, technological, and toxicological preliminary study of dog's canned food

2018 ◽  
Vol 49 (2) ◽  
pp. 110
Author(s):  
S. RANTOS (Σ. ΡΑΝΤΟΣ) ◽  
L. PANTOULAS (Λ. ΠΑΝΤΟΥΛΑΣ) ◽  
I. SARAKATSIANOS (Ι. ΣΑΡΑΚΑΤΣΙΑΝΟΣ) ◽  
G. ROZOS (Γ. ΡΟΖΟΣ) ◽  
N. PAPAIOANNOU (Ν. ΠAΠΑΪΩΑNNOΥ)
Keyword(s):  
Connective Tissue ◽  
Water Activity ◽  
Anaerobic Bacteria ◽  
Full Agreement ◽  
Canned Food ◽  
Lead And Cadmium ◽  
Preliminary Study ◽  
Soya Proteins ◽  
Aerobic And Anaerobic

During this study canned food for dogs of six firms were investigated (42 samples totally). Microbiologically the following parameters were checked: the commercial sterility, the water activity (aw), the pH, the presence of aerobic and anaerobic bacteria after incubation of tins in 25 ° C for 28 days, 32 ° C for 21 days and 55 ' C for 8 days. Histologically, the existence of different kinds of tissues was examined. Technologically Weende's analysis and separation of the tin's content were made. Toxicologically, the concentration of lead and cadmium were countered. The results showed that dog's canned food, in Greece, are supersterillised. Muscular, adipose and connective tissue are used for their production as well as byproducts and soya proteins by some firms. The results of Weende's analysis are in full agreement with the amount of nutriments that they were written on tins' labels.

Reactor Design for Complex Reactions

2001 ◽  
Author(s):  
L. K. Doraiswamy
Keyword(s):  
Batch Reactor ◽  
Plug Flow ◽  
Reaction Network ◽  
Reactor Design ◽  
Batch Reactors ◽  
Complex Reaction ◽  
Mixed Flow ◽  
Flow Reactors ◽  
Design Procedures ◽  
Reactor Types

Procedures were formulated in Chapter 5 for treating complex reactions. We now turn to the design of reactors for such reactions. Continuing with the ethylation reaction, we consider the following reactor types for which design procedures were formulated earlier in Chapter 4 for simple reactions: batch reactors, continuous stirred reactors (or mixed-flow reactors), and plug-flow reactors. However, we use the following less formal nomenclature: A = aniline, B = ethanol, C = monoethyaniline, D = water, E = diethylaniline, F = diethyl ether, and G = ethylene. The four independent reactions then become Using this set of equations as the basis, we now formulate design equations for various reactor types. Detailed expositions of the theory are presented in a number of books, in particular Aris (1965, 1969) and Nauman (1987). Consider a reaction network consisting of N components and M reactions. A set of N ordinary differential equations, one for each component, would be necessary to mathematically describe this system. They may be concisely expressed in the form of Equation 5.5 (Chapter 5), or . . . d(cV)/dt = vrV (11.1) . . . The use of this equation in developing batch reactor equations for a typical complex reaction is illustrated in Example 11.1.

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