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Published on: April 24, 2020
Advancing Internal Dosimetry in Personalized Nuclear Medicine: Toward Optimized Radiopharmaceutical Use in Clinical
1Department of Radiological Sciences, College of Applied Medical Sciences, Najran University, Najran 61441, Saudi Arabia.
Three Monte Carlo simulation codes (MCNP6, GATE, GAMOS) accurately quantified absorbed radiation doses in organs using the Medical Internal Radiation Dose (MIRD) formalism. This validated toolkit advances internal dosimetry for personalized nuclear medicine and radiopharmaceutical therapies.
Area of Science:
- Nuclear Medicine
- Medical Physics
- Computational Modeling
Background:
- Accurate quantification of absorbed radiation doses from radiopharmaceuticals in human organs is crucial for effective nuclear medicine applications.
- Direct in vivo measurement of these absorbed doses is often impractical, necessitating advanced computational methods.
- Monte Carlo (MC) simulations provide a powerful approach for simulating radiation transport and energy deposition within complex biological systems.
Purpose of the Study:
- To compare and validate three MC-based simulation codes: MCNP6, GATE, and GAMOS, for internal dosimetry calculations.
- To evaluate the performance of these codes in quantifying absorbed doses according to the Medical Internal Radiation Dose (MIRD) formalism.
- To demonstrate the adaptability of these MC frameworks for both diagnostic and therapeutic radiopharmaceutical applications.
Main Methods:
- Utilized three MC codes: MCNP6, GATE, and GAMOS, to perform internal dosimetry simulations.
- Employed the Medical Internal Radiation Dose (MIRD) formalism for dose assessment.
- Simulated 99mTc-MIBI uptake in the myocardium of an anthropomorphic phantom, assessing dose distributions in target organs at different time points.
Main Results:
- All three MC codes demonstrated strong consistency in organ-specific dose distributions.
- The pancreas, gallbladder, and kidneys consistently received the highest absorbed doses across all simulation codes.
- A consistent organ dose ranking (pancreas > gallbladder > kidneys > spleen > heart/liver) was established, corroborating empirical data.
Conclusions:
- The comparative analysis highlights the complementary strengths of MCNP6, GATE, and GAMOS for internal dosimetry.
- GATE is suitable for high-fidelity clinical applications, GAMOS for rapid prototyping, and MCNP6 as a benchmark tool.
- These MC frameworks offer a validated and adaptable toolkit for advancing internal dosimetry in personalized nuclear medicine and radiopharmaceutical therapy development.
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