I want to know the actual loading on reactor brick to simulate it in real environment.
Your question needs some specification. What do you mean by fuel brick? I assume you are referring to a block type HTR. For a block type HTR, the hexagonal graphite blocks with fuel compacts in it? Or carbon bricks like in the AVR high temperature reactor (but then you would not refer these as 'fuel bricks'?
And which loads are you referring to? Mechanical loads? Thermal loads? Neutron dose?
For the steady-state mechanical loads you would take the density * volume on top of 'brick' under consideration, for dynamic conditions, say earthquake conditions, you have to take the additional acceleration and thereby caused loads into account.
For the thermal stresses you need to determine the temperature distribution which is a function of position in the core (both axial and radial), initial heavy metal load, control rod elements position and its content of fission products (burn-up), and if the fuel element was already relocated after fuel shuffling.
Maximum irradiation dose at the end of a fuel element must also remain within certain limits because graphite initially shrinks with the fast neutron dose, then after a certain minimum will increase again. Growing to dimensions bigger than the initial block dimensions will damage the integrity of the core and this would be the maximum allowable fast neutron dose. This maximum dose is graphite specific.
What do you mean by real environment? Experiments in helium atmosphere at elevated temperatures?
Hope that this was helpful
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