Simulation of the HTR-10 reactor core with spherical fuel to obtain the minimum height to access reactor criticality

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Abbasi K.; Nayyeri M.H.

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Journal Paper

Paper Information

Journal: Journal of Nuclear Science, Engineering and Technology Year:2025 | Volume:46 | Issue:1 Page(s): 157-164

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Information Journal Paper

Title

Simulation of the HTR-10 reactor core with spherical fuel to obtain the minimum height to access reactor criticality

Author(s)

Abbasi K. | Nayyeri M.H. | Issue Writer Certificate

Keywords

Pebble bed reactor

Criticality height

Neutron Flux

MCNP Code

Abstract

The HTR-10 reactor is an experimental Pebble bed reactor (PBR), where simulating the Neutron Flux is crucial due to the reactor's multiple advantages, including safety, high efficiency, and modularity. As a result, studying and researching such reactors is a significant focus for countries with nuclear technology, especially for commercialization. Since both the fuel and moderator are in the form of spherical pebbles and are randomly distributed in the core, accurately evaluating the Neutron Flux is vital. This evaluation involves calculating the minimum height required for the reactor’s criticality, based on the specific arrangement of fuel and moderator. In this study, a new method for arranging the fuel and moderator pellets, while maintaining a ratio of 43:57, has been proposed. The calculations were performed using the MCNP Code. Helium gas was chosen as the coolant, and changes in reactivity due to the insertion of control rods were also calculated.

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