Estimation of the absorbed dose of two thermoluminescent borates to monoenergetic neutrons
Creators
- 1. Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica, Doctorado en Ingenieria y Tecnologia Aplicada, Av. Ramon Lopez Velarde 801, Col. Centro, 98000 Zacatecas, Zac. (Mexico)
- 2. Conacyt, Centro de Investigaciones Biologicas del Noroeste, Playa Palo de Santa Rita Sur, 23090 La Paz, Baja California Sur (Mexico)
Description
Neutrons are used in medicine, analytical chemistry, biology, materials study, etc. Neutrons have a high radiobiological efficiency so exposure to them represents a health risk. To design safe protocols for use, handling and shielding against neutrons is necessary to know their spectrum or, failing that, measure the dose. For this, different instruments are used as passive and active detectors, in our group Magnesium Borate (MBO) compounds with thermoluminescent properties were synthesized against 137Cs gammas and 241 AmBe neutrons. The objective of this work was to determine the response to the absorbed dose of MBO:Dy and MBO:Dy,Na as detectors of thermal neutrons in an area monitor before monoenergetic neutrons. The response function was estimated using Monte Carlo methods for 47 monoenergetic neutrons (1E(9) up to 20 MeV). The area monitor is a 20.32 x 20.32 cm polyethylene cylinder. We found that the absorbed dose response of MBO:Dy is slightly greater than that of MBO:Dy,Na. Furthermore, neutron capture is the interaction that occurs most likely. (Author)
Files
52029911.pdf
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Additional details
Additional titles
- Original title (Spanish)
- Estimacion de la dosis absorbida de dos boratos termoluminiscentes ante neutrones monoenergeticos
Publishing Information
- Publisher
- Sociedad Mexicana de Irradiacion y Dosimetria
- Imprint Place
- Mexico City (Mexico)
- Imprint Pagination
- 10 p.
- Report number
- INIS-MX--3393
Conference
- Title
- 20. international symposium on solid state dosimetry
- Acronym
- ISSSD 2020
- Dates
- 7-11 Dec 2020
- Place
- Mexico City (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 52029911
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABSORBED RADIATION DOSES; BIOLOGY; BORATES; CAPTURE; CESIUM 137; CHEMISTRY; CYLINDERS; EFFICIENCY; HEALTH HAZARDS; INTERACTIONS; MAGNESIUM; MEDICINE; MEV RANGE; MONITORS; MONTE CARLO METHOD; NEUTRON REACTIONS; POLYETHYLENES; RESPONSE FUNCTIONS; SHIELDING; THERMAL NEUTRONS
- Descriptors DEC
- ALKALINE EARTH METALS; BARYON REACTIONS; BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BORON COMPOUNDS; CALCULATION METHODS; CESIUM ISOTOPES; DOSES; ELEMENTARY PARTICLES; ELEMENTS; ENERGY RANGE; FERMIONS; FUNCTIONS; HADRON REACTIONS; HADRONS; HAZARDS; INTERMEDIATE MASS NUCLEI; ISOTOPES; MEASURING INSTRUMENTS; METALS; NEUTRONS; NUCLEAR REACTIONS; NUCLEI; NUCLEON REACTIONS; NUCLEONS; ODD-EVEN NUCLEI; ORGANIC COMPOUNDS; ORGANIC POLYMERS; OXYGEN COMPOUNDS; POLYMERS; POLYOLEFINS; RADIATION DOSES; RADIOISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Funding organization
- Sociedad Mexicana de Irradiacion y Dosimetria (Mexico)