OpenDose

OpenDose provides validated Specific Absorbed Fractions (SAFs) and computed S values for nuclear medicine dosimetry to support estimation of energy deposition from radiopharmaceutical sources in ICRP Publication 110 adult reference models.

Key Features:

• Collaborative validation: Eighteen international teams contributed to generation and cross-validation of dosimetric data.
• Monte Carlo radiation transport: Dosimetric calculations were performed using EGSnrc/EGS++, FLUKA, GATE, Geant4, MCNP/MCNPX, and PENELOPE.
• Specific Absorbed Fractions (SAFs): SAFs were produced for all source region and target combinations of the ICRP Publication 110 adult reference models.
• S values from decay data: Monoenergetic SAFs were combined with radionuclide decay data from ICRP Publication 107 to calculate S values.
• Inter-code agreement and statistics: SAFs computed across codes show good agreement, with standard deviations below individual statistical uncertainties.
• Relational dosimetric dataset: The dataset includes SAFs with statistical uncertainties and S values for 1,252 radionuclides stored in a relational database.
• Benchmarking against reference software: Calculated S values were compared with OLINDA/EXM 2.0 and IDAC-Dose 2.1 and show agreement with those tools.

Scientific Applications:

• Radiopharmaceutical dosimetry: Provides SAFs and S values for dose estimation in radiopharmaceutical therapy and diagnostic procedures.
• Method validation and benchmarking: Supports inter-code comparison and validation of Monte Carlo radiation transport and dosimetric calculations.
• Personalized dosimetry and safety assessment: Supplies reference data for patient-specific absorbed dose estimation and evaluation of radiation safety in nuclear medicine.

Methodology:

Monte Carlo simulations using EGSnrc/EGS++, FLUKA, GATE, Geant4, MCNP/MCNPX, and PENELOPE were used to compute monoenergetic SAFs for all source–target combinations in the ICRP Publication 110 adult reference models; S values were derived from these SAFs using radionuclide decay data from ICRP Publication 107, and inter-code statistical comparisons were performed showing standard deviations below individual statistical uncertainties.