Presentation of a semiempirical method for the calculation of doses due to neutrons and capture gamma rays inside high energy accelerators rooms
Creators
- 1. Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)
Description
Full text: Medical electron accelerators operating above 10 MeV produce radiation beams that are contaminated with neutrons. Therefore, shielding design for high energy accelerator rooms must consider the neutron component of the radiation field. In this paper a semiempirical method is presented to calculate doses due to neutrons and capture gamma rays inside the room and the maze. The calculation method is based on the knowledge of the neutron yield Q (neutrons/Gy of photons at isocenter) and the average energy of the primary beam of neutrons Eo (MeV). The method constitutes an appropriate tool for shielding facilities evaluation. The accuracy of the method has been contrasted with data obtained from the literature and an excellent correlation among the calculations and the measured values was achieved. In addition, the method has been used in the verification of experimental data corresponding to a 15 MeV linear accelerator installed in the country with similar results. (author)
Abstract (Spanish)
Texto completo: Se ha visto que los aceleradores lineales de uso medico que operan con energias de fotones y/o electrones superiores a 10 MeV, producen haces de radiacion contaminados con neutrones. Por lo tanto en el disenio de recintos blindados para albergar este tipo de equipos, debera considerarse la componente neutronica del campo de radiacion. En este trabajo se presenta un metodo semiempirico que permite calcular dosis debida a neutrones en el interior del recinto blindado que alberga el acelerador y la dosis debida a neutrones y gamma de captura neutronica en el interior del laberinto. El metodo de calculo de dosis en el interior del recinto blindado se basa en el conocimiento del rendimiento neutronico Q (neutrones/Gy de fotones en isocentro) del acelerador en cuestion y de la energia promedio del haz primario de neutrones Eo (MeV), y constituye una herramienta adecuada para la evaluacion del blindaje de recintos para aceleradores lineales de uso medico, tarea que compete a la Autoridad Regulatoria Nuclear. La validez del metodo ha sido contrastado con datos obtenidos de la literatura, lograndose una excelente correlacion entre los valores medidos y calculados y se lo ha empleado en la verificacion de datos experimentales correspondientes a un acelerador lineal instalado en el pais que opera con energia de fotones de 15 MeV. (autor)Files
30057756.pdf
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Additional details
Additional titles
- Original title (Spanish)
- Presentacion de un metodo semiempirico de calculo de dosis debida a neutrones generados en aceleradores lineales de uso medico
Publishing Information
- Publisher
- SAR
- Imprint Place
- Buenos Aires (Argentina)
- Imprint Title
- Proceedings of the 6. Argentine congress on radiation protection and nuclear safety
- Imprint Pagination
- 75 p.
- Journal Page Range
- p. 55
- Report number
- INIS-AR--137
Conference
- Title
- 6. Argentine congress on radiation protection and nuclear safety
- Original Conference Title
- 6. Congreso argentino de proteccion radiologica y seguridad nuclear
- Dates
- 22-24 Sep 1998
- Place
- Buenos Aires (Argentina)
INIS
- Country of Publication
- Argentina
- Country of Input or Organization
- Argentina
- INIS RN
- 30057756
- Subject category
- S43: PARTICLE ACCELERATORS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATORS; CAPTURE; DOSIMETRY; ELECTRON BEAMS; ELECTRONS; GAMMA SOURCES; MEDICAL ESTABLISHMENTS; RADIATION DOSES; RADIOTHERAPY; SHIELDING
- Descriptors DEC
- BEAMS; ELEMENTARY PARTICLES; FERMIONS; LEPTON BEAMS; LEPTONS; MEDICINE; PARTICLE BEAMS; RADIATION SOURCES; THERAPY
Optional Information
- Notes
- Imprint:Actas del 6. congreso argentino de proteccion radiologica y seguridad nuclear