New route in TRIPOLI-4 for radiation dosimetry calculations using ICRP 100 voxel phantoms
- 1. Universite Paris-Saclay, CEA, Service d'Etudes des Reacteurs et de Mathematiques Appliquees - SERMA, 91191 Gif-sur-Yvette (France)
Description
The TRIPOLI-4 Monte Carlo radiation transport code has been widely used in the radiation shielding, criticality safety and fission reactor physics fields to support French nuclear energy research and engineering projects. With the growing interest in using the TRIPOLI-4 code for radiation protection, radiation dosimetry, and medical application fields, the radiation dose calculations in organ-tissue level are in progress. Computational human phantoms are available from the International Commission on Radiological Protection (ICRP) report 110. These voxel phantoms have been modeled with TRIPOLI-4 using its lattice geometry options. In this study, a new route has been developed in TRIPOLI-4 and its graphical tool T4G in order to simplify the usage of voxel phantoms. An effort was made in the new route to optimize the lattice practice in modeling and to improve the particle tracking efficiency for voxel phantoms. The interactive T4G could thus display iteratively in a fast way to verify the voxel source and target organs on materials and positions. A brief analysis of current voxel-phantom irradiation scenarios for organ dose calculations was presented. Verification and validation study of this new route was conducted. Various application cases were investigated using external and internal radiation sources including typical nuclides 60Co, 99mTc, 18F, 131I, and 16N. (authors)
Availability note (English)
Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)Additional details
Publishing Information
- Publisher
- ANS - American Nuclear Society
- Imprint Place
- La Grange Park (United States)
- Imprint Title
- Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering - M and C 2021
- Imprint Pagination
- 2418 p.
- Journal Page Range
- p. 804-813
Conference
- Title
- International conference on mathematics and computational methods applied to nuclear science and engineering
- Acronym
- M and C 2021
- Dates
- 3-7 Oct 2021
- Place
- Raleigh, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54081743
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANIMAL TISSUES; COMPUTERIZED SIMULATION; DOSIMETRY; ICRP; IRRADIATION; ITERATIVE METHODS; MONTE CARLO METHOD; ORGANS; PHANTOMS; RADIATION DOSES; RADIATION PROTECTION; RADIATION SOURCES; RADIATION TRANSPORT; SHIELDING
- Descriptors DEC
- BODY; CALCULATION METHODS; DOSES; INTERNATIONAL ORGANIZATIONS; MOCKUP; SIMULATION; STRUCTURAL MODELS
Optional Information
- Notes
- 15 refs.; Virtual meeting