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The maximum thermal flux at the reflector region is almost the same.
Target analysis was performed by irradiating it at a location of maximum thermal flux available in the core.
More specifically, the goal is to maximize the maximum thermal flux to power ratio in a moderate power reactor design maintaining, or even enhancing, other design aspects that are desired in a modern state of the art multi-purpose facility.
It is shown that while using the standard, low enriched uranium as fuel, the maximum thermal flux per MW of power for the core design suggested and analyzed here is greater than those found in existing state of the art facilities without detrimentally affecting the other design specs.
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In existing Apsara, the maximum thermal neutron flux level is about 1 × 1013 n/cm2/s at designed power (1 MW) whereas in upgraded version, flux will be 6.1 × 1013 n/cm2/s.
The aim of this research is to design the best geometry and to choose materials for thermal neutron collimator so as to obtain a uniform beam, high L/D ratio and a maximum thermal neutron flux at the object plane.
A conceptual design study has been developed for each of these three fluids, with the aim to evaluate the maximum allowable thermal flux at the divertor target plate and the R&D requirements for each solution.
Finally, a more compact version of the asymmetric core is developed where a maximum (non-perturbed) thermal flux of 5.0 × 1014 n cm−2 s−1 is achieved.
Finally, proper sites are determined in order to achieve maximum thermal and fast neutron flux.
Numerical results are presented to study the effect of applied thermal flux, electric field and magnetic field on the crack propagation path by using the maximum energy release rate criterion.
Solutions for a flat thermal flux in a two-group diffusion model are found for a range of assumptions, since this is a requisite for both a minimum and a maximum fuel loading in the model.
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