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ISSN Print: 1091-028X
ISSN Online: 1934-0508
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NEUTRON DIFFUSION ANALYSIS OF A FUEL PEBBLE WITH VOLUME AVERAGING METHOD
ABSTRACT
The nuclear reactor is a highly heterogeneous system where the nuclear and heat transfer processes take place at multiple scales. With the volume-averaged method, a nuclear reactor can be upscaled. However, with this methodology one integro-differential mathematical model is obtained containing more unknown variables, i.e., dependent variables with respect to the nonaveraged model. Thus, in order to obtain one upscaled and closed neutron diffusion equation, we present the closure problems that were numerically solved to compute the effective coefficients. These closure problems are defined as integro-differential boundary-value problems at microscale. In order to demonstrate the applicability of the theory, we solved the closure problems and computed effective coefficients for a Generation IV nuclear reactor containing pebble bed nuclear fuel. The results obtained with the volume-averaged model agree well with those from the classic diffusion theory and Boltzmann's equation.
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