8b544e8f-0bf8-4058-a572-4ec29d7c1b0e20251119124619009wseas:wseasmdt@crossref.orgMDT DepositInternational Journal of Chemical Engineering and Materials2945-051910.37394/232031https://wseas.com/journals/cem/32620253262025410.37394/232031.2025.4https://wseas.com/journals/cem/2025.phpMd MinhazulMostafaDepartment of Nuclear Science and Engineering Military Institute of Science and Technology (MIST) Mirpur-1216, Dhaka BANGLADESHhttps://orcid.org/0009-0008-4101-160XA. S.MollahDepartment of Nuclear Science and Engineering Military Institute of Science and Technology (MIST) Mirpur-1216, Dhaka BANGLADESHIn a nuclear reactor, gamma rays are produced primarily by nuclear fission and neutron capture on an atomic nucleus. Although fission produces considerable radioactivity, a number of barriers are used to maintain the radiation dose at a safe level. For the (n, γ) reaction, the neutrons penetrate the RPVs and other structural shielding materials producing further gamma rays. The application of multiple shielding layers increases attenuation and consequently reduces dose rates in confined spaces. This study investigates the interactions between gamma rays and diverse shielding materials through comprehensive simulations and analyses to assess their efficacy in attenuating radiation. Geant4, a powerful tool for particle simulation, plays a pivotal role in predicting and optimizing the shielding properties of these materials. The findings contribute valuable insights to the field of radiation protection, offering advancements in the design and application of nuclear shielding materials across a range of contexts and industries. The methodology involves the development of a Geant4-based simulation model that accurately represents the experimental setup. This model incorporates details of the gamma-ray radiation source, shielding materials, and the surrounding environment. Monte Carlo simulations are performed to track the trajectory of gamma rays, allowing for the determination of radiation dose rates at specified locations and aiming to enhance reactor safety and radiation protection measures as per IAEA guidelines and regulatory dose limits.111920251119202512012810https://wseas.com/journals/cem/2025/a20cem-010(2025).pdf10.37394/232031.2025.4.10https://wseas.com/journals/cem/2025/a20cem-010(2025).pdf10.1088/1757-899x/555/1/012008M. Arif Sazali, N. K. Alang Md Rashid, and K. Hamzah, A review on multilayer radiation shielding, IOP Conf. Ser.: Mater. Sci. Eng., vol. 555, no. 1, p. 012008, June 2019, doi: 10.1088/1757-899X/555/1/012008. 10.2172/4827123C. L. Whitmarsh, Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design. Oak Ridge National Laboratory for the U.S. Atomic Energy Commission, 1962. D. R. McAlister, Neutron Shielding Materials, 2018. 10.1088/1757-899x/903/1/012051D. Kovács and D. 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