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Mixing part has been taken care off and CVCS and RHRS can now be modeled 4. The program will have the capabilities of selecting any kind of material for its components. That way various simulations can be done and will aid in cost cutting of expensive experiments. 5. When fully functional the code will generate enough data to set up Design of Experiments (DOE) and Factorial experiments can be done. Based on this Optimization algorithms can be developed using Non Linear programming and Dynamic Programming to optimize plant parameters like pressure, temperature Velocity of the coolant and Concentration of chemical species for maximum output and minimum corrosion.

E. Mesmer, C. F. Baes, anf F. H. Sweeton, J. Phys. ,74, 1937 (1970). P. Cohen, “Water Coolant Technology of Power Reactors”, Amer. Nucl. , La Grange park, IL, 1985. A. J. Elliot, “Rate Constants and G-Values for the Simulation of the Radiolysis of Light Water Over the Range 0-300 oC”, AECL Report No. 11073 (Oct. 1994). Atomic Energy of Canada Ltd. D. D. Macdonald, J. Electrochem. , 139, 3434 (1992). K. Radhakrishnan and A. C. Hindmarsh, “Description and Use of LSODE, the Livermore Solver for Ordinary Differential Equations”, NASA Reference Publication 1327, 1993.

Engelhardt, G. D. Macdonald, and P. Millett, “Transport Processes in Steam Generator Crevices. I. General Corrosion Model”, Corros. , 41, 2165-2190 (1999) [36]. Engelhardt, G. D. Macdonald, and P. Millett, “Transport Processes in Steam Generator Crevices. II. A Simplified Method for estimating Impurity Accumulation Rates”, Corros. , 41, 2191-2211 (1999) [37]. , I. D. J Millett, “Transport processes in Steam Generator Crevices. III. Experimental results”, Corros. , 44, 191-205 (2002) 46 Task 3. 1 The ECP and CGR Models in BWR.

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Electrochemistry of Water-Cooled Nuclear Reactors


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