this is a MAthlab question hi, im in a little conundrum, im taking this class as an elective because i dint have another option, im
this is a MAthlab question hi, im in a little conundrum, im taking this class as an elective because i dint have another option, im terrible at creating code, if i see the code and i read all the lines i can tell what everything is doing but the actual making of it i cant do it to save my life, from this problem i can create the plate insert the geometry and parameters but whenever you export your variables to the workplace i dont know where to go from there, i really dont know where to start, or how to start my code in order to get what he want us to display or calculate, what i really need is to see how somebody that knows would attack this problem, maybe im doing stuff wrong even in the geometry and parameters entry i dont know im panicking a little im terrible at writing code, so could you pleeease attack this problem from the beginning and show me how your you write your code to get what he wants so i can make notes about it
MC A nuclear fuel element is of plate geometry. It is desired to investigate the effects of fuel offsct within the cladding. For simplicity, assume uniform heat generation in the fuel, temperature- independent fuel conductivity, and heat conduction only in the gap. Calculate The temperature difference between the offset fuel and the concentrie fuel maximum temperatures: TMo-TMc. 1. 2. The temperature differenee between the cladding maximum temperatures: T -T4. 3. The ratio of heat fluxes to the coolant. q/qi and q/q 4. Plot the temperature profiles of both cases in one figure with axes labels and units. 5. Use MATLAB PDE Toolbox to solve this problem. Model the left half gcometry of the case (a) to take the advantage of the symmetry. Construct two models, rename the shape object names to AB01, AB02, etc., where AB are your name initials (like Adam Bieber). Export case 1 solutions as p, e, t, u, then export case 2 solutions as pl, el, t1, u1 Construet one m file to calculate the requested information and display them in the MATLAB command window and produce the requested plot. 6. Submit a zip file (Last Pirst Hwo1.zip) to blackboard. The .zip file should contain four files as follows Case a model Case b model Last First HW01 model a.m Last First HW01 model b.m Last First Hw01 post. Last First HW01 ts for docx or Rc with answers and figures Troolant and heat transfer coefficient to coolant may be assumed constant on both sides and for both cases. Neglect interface contact resistance for fuel and cladding. 3.011 WmC(PuO-UO2) kg-0.289 wucc (He) ke 21.63 Wmc (SS) D 6.352 mm Dg 6.428 mm Cladding Pellet 0.4054 min 9.313 105 kWm bsolan 113.6 kWm2-C (Na) 500K MC A nuclear fuel element is of plate geometry. It is desired to investigate the effects of fuel offsct within the cladding. For simplicity, assume uniform heat generation in the fuel, temperature- independent fuel conductivity, and heat conduction only in the gap. Calculate The temperature difference between the offset fuel and the concentrie fuel maximum temperatures: TMo-TMc. 1. 2. The temperature differenee between the cladding maximum temperatures: T -T4. 3. The ratio of heat fluxes to the coolant. q/qi and q/q 4. Plot the temperature profiles of both cases in one figure with axes labels and units. 5. Use MATLAB PDE Toolbox to solve this problem. Model the left half gcometry of the case (a) to take the advantage of the symmetry. Construct two models, rename the shape object names to AB01, AB02, etc., where AB are your name initials (like Adam Bieber). Export case 1 solutions as p, e, t, u, then export case 2 solutions as pl, el, t1, u1 Construet one m file to calculate the requested information and display them in the MATLAB command window and produce the requested plot. 6. Submit a zip file (Last Pirst Hwo1.zip) to blackboard. The .zip file should contain four files as follows Case a model Case b model Last First HW01 model a.m Last First HW01 model b.m Last First Hw01 post. Last First HW01 ts for docx or Rc with answers and figures Troolant and heat transfer coefficient to coolant may be assumed constant on both sides and for both cases. Neglect interface contact resistance for fuel and cladding. 3.011 WmC(PuO-UO2) kg-0.289 wucc (He) ke 21.63 Wmc (SS) D 6.352 mm Dg 6.428 mm Cladding Pellet 0.4054 min 9.313 105 kWm bsolan 113.6 kWm2-C (Na) 500K
