Diseño de filtros en un haz radial del Reactor Triga Mark III para neutrones epitérmicos
Currently in the world there are millions of people living with cancer. Glioblastoma multiforme is the most common and aggressive of brain tumors and is very difficult to treat with surgery, chemotherapy, or conventional radiation therapy. The only viable alternative is a treatment through Boron Neu...
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| Tipo de recurso: | tesis doctoral |
| Estado: | Versión publicada |
| Fecha de publicación: | 2022 |
| País: | México |
| Institución: | Universidad Autónoma de Zacatecas |
| Repositorio: | Repositorio Institucional Caxcán |
| Idioma: | español |
| OAI Identifier: | oai:http://ricaxcan.uaz.edu.mx:20.500.11845/2938 |
| Acceso en línea: | http://ricaxcan.uaz.edu.mx/jspui/handle/20.500.11845/2938 http://dx.doi.org/10.48779/ricaxcan-57 |
| Access Level: | acceso abierto |
| Palabra clave: | CIENCIAS FISICO MATEMATICAS Y CIENCIAS DE LA TIERRA [1] BNCT Filtro Neutrones MCNP TRIGA Mark III Filter Neutrons |
| Sumario: | Currently in the world there are millions of people living with cancer. Glioblastoma multiforme is the most common and aggressive of brain tumors and is very difficult to treat with surgery, chemotherapy, or conventional radiation therapy. The only viable alternative is a treatment through Boron Neutron Capture Therapy, which requires a drug with 10 B and a modulated neutron beam. One of the problems associated with this therapy is having a neutron beam with the proper flux and spectrum. At the Instituto Nacional de Investigaciones Nucleares, there is a TRIGA Mark III nuclear research reactor that has several irradiation beams. In this work, the Monte Carlo code MCNP5 and MCNP6 were used to simulate and study the effect of filters on the neutron spectrum produced in the beam tube “East 1” of this reactor, using different materials, and in different positions along of the tube. Of the different combinations used, the best results were Cases A and B, where each filter was made with the same amount and type of materials: steel and graphite for filter 1, and aluminum and cadmium for filter 2. In both cases, filter 2 was the same (Cd + Al + Cd), but in filter 1, in Case A, it was 30 cm of steel and 30 cm of graphite, while, for Case B, it was 15 cm of steel, 15 cm of graphite, 15 cm of steel and 15 cm of graphite. Neutron spectra were calculated at three sites along the beam tube and two sites outside the beam tube; here, the environmental equivalent dose, the personal equivalent dose and the effective dose were also estimated. At the distance of 517 cm, in Case B, the result is a fluence ratio between epithermal and thermal neutrons of 30.39, being greater to 20 recommended by the International Atomic Energy Agency. |
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