Published 1998 | Version v1
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Presentation of a semiempirical method for the calculation of doses due to neutrons and capture gamma rays inside high energy accelerators rooms

  • 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)

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Part of:
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety

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