Neutron transport codes are an integral part of reactor physics calculation. The freely available lattice code DRAGON results from an effort to unify inside a single computer code various well-established numerical techniques and calculation methodologies which are commonly used to solve the neutron transport equation. It is of utmost importance for the user community, both from safety and operation point of view, that the codes being utilised for neutronic calculations maintain a high degree of confidence in their predictions. Benchmark problems are designed to test the capability of a neutronic code by comparing the results obtained from the code with well-established results, either from experimentation or from other validated neutronic codes. After PWRs, BWRs, and PHWRs are two of the most popular types of nuclear reactors currently in use worldwide. Consequently, the ability to perform accurate neutronic calculation involving these lattice types can be deemed as a necessary requirement in most modern lattice codes. In this work, we will study two benchmark problems based on the aforementioned reactor lattice types. Using the lattice code DRAGON and subsequently comparing the results with available published solutions, we aim to ascertain the capability of DRAGON to effectively simulate both of these two types of lattices with fresh and burnt fuel.
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The authors would like to thank Dr. P. V. Varde, former Associate Director, Reactor Group and Shri C. G. Karhadkar, Associate Director, Reactor Group for their unfailing support and continuous encouragement.
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Banerjee, S., Singh, T. Study of PHWR and BWR lattice benchmark problems with multigroup multidimensional neutron transport code dragon. Life Cycle Reliab Saf Eng (2020) doi:10.1007/s41872-019-00108-w
- Benchmark problem
- Lattice code validation
- DRAGON 5 code
- Neutron transport