This study compares computational approaches for gamma radiation shielding design in medical concrete barriers, focusing on high-activity Cobalt-60 (Co-60) teletherapy sources—still relevant in resource-limited settings despite the global shift to linear accelerators. An open-source Python-based Monte Carlo framework was developed to model photon transport through standard concrete (density 2.35 g/cm³), incorporating NIST XCOM energy-dependent cross-sections, explicit dual gamma emissions of Co-60 (1.173 MeV and 1.332 MeV), material composition effects, and buildup factors using ANSI/ANS-6.4.3 Berger parameters. The framework was validated against NIST XCOM data (agreement 3% at Co-60 energies), narrow-beam Beer-Lambert law (2% deviation), and OpenMC benchmarks using the ENDF/B-VIII.0 nuclear data library (agreement within 1.2–8%, ~7.4% difference at 195 cm). Compared to the conservative NCRP Report 49 regulatory method—which employs simplified assumptions and built-in safety margins for compliance—the Monte Carlo approach required 195 cm of concrete for a representative 10,000 Ci Co-60 source at 5 m from an occupied area (dose constraint 0.1 μSv/h), versus 147 cm by NCRP 49—a 33% difference. This arises mainly from explicit dual-energy modeling (~15%), detailed buildup inclusion in thick shields (~65%), and precise cross-sections (~20%). While NCRP 49 (and successor NCRP 151) provides practical, conservative tools for routine shielding design, Monte Carlo simulations deliver enhanced physical accuracy for thick barriers and high-activity sources. The findings advocate complementary use: regulatory methods for compliance documentation and Monte Carlo for design optimization. This work offers an accessible open-source Python tool and evidence-based recommendations for clinical shielding workflows, while noting Co-60’s ongoing relevance in select global contexts (IAEA DIRAC data).
Oo et al. (Tue,) studied this question.