Optimization of Neutron Flux in Nuclear Reactors: Monte Carlo Simulations of Coolant and Moderator Admixture Effects

Optimization of Neutron Flux in Nuclear Reactors: Monte Carlo Simulations of Coolant and Moderator Admixture Effects

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In order to regulate the fission reaction, maintain ideal reactor temperatures, and guarantee safe operation, fission reactors require the use of appropriate coolant and moderator materials. Materials such as graphite, heavy water (D2O), and light water (H2O) are frequently used as moderators as they are efficient to transfer much heat energy from fast neutrons in fission chain reaction, thereby increasing the possibility of additional fission chain reactions. A good moderator must absorb a small number of neutrons while slowing them down. A variety of materials with distinct thermal and physical characteristics are employed as coolants, including water, helium, liquid metals, and molten salts. Both Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs) use light water as the coolant and moderator. To make these materials safer, more effective, and more sustainable for future, contemporary reactors. It is interesting to study how to enhance further their heat transfer capability. With this aim, in the present study the solvent is used in light water to enhance its thermal efficiency without increasing its neutron capture cross section. In the work reported here, the uranium watt fission spectrum is used to examine the thermal and total neutron spectra following the addition of yttrium(III) nitrate (Y(NO3)(3)) to light water (H2O). As Y(NO3)(3) can increase thermal efficiency of light water solution, the results can be useful to decide right proportion of the solvent. The results of this investigation are essential for the development of next generation sophisticated reactors.

In order to regulate the fission reaction, maintain ideal reactor temperatures, and guarantee safe operation, fission reactors require the use of appropriate coolant and moderator materials. Materials such as graphite, heavy water (D2O), and light water (H2O) are frequently used as moderators as they are efficient to transfer much heat energy from fast neutrons in fission chain reaction, thereby increasing the possibility of additional fission chain reactions. A good moderator must absorb a small number of neutrons while slowing them down. A variety of materials with distinct thermal and physical characteristics are employed as coolants, including water, helium, liquid metals, and molten salts. Both Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs) use light water as the coolant and moderator. To make these materials safer, more effective, and more sustainable for future, contemporary reactors. It is interesting to study how to enhance further their heat transfer capability. With this aim, in the present study the solvent is used in light water to enhance its thermal efficiency without increasing its neutron capture cross section. In the work reported here, the uranium watt fission spectrum is used to examine the thermal and total neutron spectra following the addition of yttrium(III) nitrate (Y(NO3)(3)) to light water (H2O). As Y(NO3)(3) can increase thermal efficiency of light water solution, the results can be useful to decide right proportion of the solvent. The results of this investigation are essential for the development of next generation sophisticated reactors.

Fission reactor; Reactor moderator material; Reactor coolant material; PHITS simulation; MCNP simulation

Fission reactor; Reactor moderator material; Reactor coolant material; PHITS simulation; MCNP simulation

MAKWANA, R.; SONI, B.; UNAGAR, V.; MUKHERJEE, S.; KATOVSKÝ, K.; PUROHIT, A.; SINGH, N.

2026

01.01.2025

IEEE

NEW YORK

979-8-3315-8637-9

International Scientific Conference on Electric Power Engineering

Proceedings of the ... International Scientific Conference on Electric Power Engineering

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