IPEN: Modifica párrafo 611 de la Norma Técnica N° PR.002.2011 “Requisitos Técnicos y Administrativos para los Servicios de Dosimetría Personal de Radiación Externa”

Según la Resolución de Presidencia Nº 132-11-IPEN (09 de junio de 2011) el párrafo 611 de la Norma Técnica N° PR.002.2011 “Requisitos Técnicos y Administrativos para los Servicios de Dosimetría Personal de Radiación Externa” disponía:

"611. Los dosímetros con dosis mayores a 50 mSv y  que pueden ser  re­leídos, se conservarán durante un año." /1/

Mediante Resolución de Presidencia Nº 240-12-IPEN se ha modificado el párrafo 611 de la Norma Técnica N° PR.002.2011, que ha quedado redactado de la manera siguiente:

 “611. En caso que se presenten reportes de dosis mayores a 50 mSv, el proveedor del servicio debe otorgar las facilidades que requiera específicamente la Oficina Técnica de la Autoridad Nacional para realizar la verificación del proceso”. /2/

La referida Norma Técnica fue aprobada el año 2011 por Resolución de Presidencia Nº 132-11-IPEN/PRES y contiene los requisitos administrativos y técnicos  que deben cumplir los servicios de dosimetría externa de radiaciones, con fines de autorización por parte de la Oficina Tecnica de la Autoridad Nacional, siendo de aplicación para las entidades u organizaciones que llevan o vayan a llevar a cabo servicios de dosimetría personal de radiación externa a nivel nacional.

Teniendo en cuenta que el IPEN es el promotor de las bondades de la tecnología nuclear y quien contribuye con la protección de la población de los riesgos que involucran las radiaciones ionizantes, ha tenido, desde los inicios de la actividad nuclear en el país, una especial preocupación por la salud y bienestar de quienes están ocupacionalmente expuestos a radiaciones, por tal motivo realiza diversas acciones que permitan mantener e incrementar la cultura de prevención en materia de seguridad y salud, que comprende una serie de protocolos que deben ser estrictamente cumplidos por los respectivos usuarios.

Fuente:

/1/ http://www.ipen.gob.pe/site/regulacion/normatividad/nsr_PR002-2011.pdf

/2/ Resolución de Presidencia Nº 240-12-IPEN.

 http://www.ipen.gob.pe/site/noticias/2012/24set2012.html

Accident in industrial radiography. Chilca, Lima - Peru. 12 January 2012.

Accident in industrial radiography

Posted on: 23 July 2012

Event Date:	12 January 2012	Event Type:	Radiation Source
Event Location:	Peru, Chilca, Lima	INES Rating:	3 (Provisional)

A radiographer was taking several radiographic films to pipes by the night. In order to be sure that the guide tube was correctly aligned the radiographer approached to the guide tube and collimator to fix them over the pipe. This operation was repeated by 40 times. Eventually the radiographer touched the tip of guide tube with his left hand where the source was unnoticed disengaged, at least 10 times. Also, as radiographer performed this operation two auxiliary staff approached to him carrying the films to be placed for the radiography, at least by 20 to 40 times. The radioactive source was 3199,5 GBq of 192Ir. The event was detected at the end of the job and the radiographer advised to the safety officer who jointly with other licensed operator recovered the radioactive source in a safely manner. Operator showed mild symptoms as nausea and vomiting at the end of job. The other auxiliary people showed just nausea symptoms. The symptoms finished after some hours. The finger of the operator showed blistering at the fifth day. Based in biological dosimetry the radiographer received a whole body doses of 1,86 Gy. The dose to his left hand was 35 Gy as average but the dose to the distal falange (finger) was 70 Gy, both based on electron paramagnetic resonance (EPR). The doses to assistants were 0,45 Gy and 0,75 Gy to whole body, based on biological dosimetry. The personnel were promptly admitted to the hospital for clinical analysis and medical examination. The operator was after derived to France (Percy Militar Hospital) for treatment but part of his finger was amputated. Currently he has returned to Peru and, according the medical evaluation, his health is good stable and going to recovery, but psychological treatment has been advised. The assistants are just under out-patient medical follow up.
______________________________________ 
A radiographer was taking several radiographic films to a pipes by the night. In order to be sure that the guide tube was correctly the radiographer went to the tube guide an collimator to fix them. This operation was made by 40 times. Eventually the radiographer touched with his left hand, at least 10 times, the tube guide where the source was unnoticed. Also, two auxiliar staff went to the radiographer position carrying the films to be checked at least by 40 and 20 times. The radioactive source was 3199,5 GBq Ir-192. The event was detected at the end of job. The radiographer adviced to radioprotection officer who jointly to other operator rescued the radiactive source in safely manner. Operator showed mild symptoms as nausea and womiting and other just nausea, but after all this symptoms are finished. The finger of operator showed a blistering at the fifth day. Based in first calculations, symptoms and dosimeter reading the operator could have received 6 - 7 Gy to whole body and > 50 Gy to finger. The other personnel could have received doses from 1 to 3 Gy. Currently the personnel is being admitted to the hospital and citogenetic dosimetry will be performed to adjust the doses.

INES Rating: 3 - Serious incident (Provisional) as per 17 January 2012

Impact on people and the environment
Release beyond authorized limits?	No
Overexposure of a member of the public?	No
Overexposure of a worker?	Yes
Impact on the radiological barriers and controls at facilities
Contamination spread within the facility?	No
Damage to radiological barriers (incl. fuel damage) within the facility?	No
Degradation of Defence In-Depth	No
Other information
Person injured physically or casualty?	Yes
Is there a continuing problem?	No

Contact Person for Further Information

Renan Ramirez  Instituto Peruano de Energia Nuclear

rramirez@ipen.gob.pe

Source: http://www-news.iaea.org/ErfView.aspx?mId=c7e52c89-bdff-4fb4-bfed-02392b70b53e 

Dose re-estimation by method in TLD

The Effects of Photon Energy and Irradiation History on the Efficiency of Dose Re-Estimation in CaSO₄:Dy Teflon Discs Using Repeated Read-outs

1. A.R. Lakshmanan and 
2. R.C. Bhatt

Abstract

Since Teflon is a bad conductor of heat, in many readers the thermoluminescence of a CaSO₄ Teflon TLD disc is erased only partially during the first read-out; the second and even the third TL read-outs are functions of the absorbed dose. This offers a simple method of re-estimation of absorbed dose. The present study has shown that, as might be expected, the efficiency of dose re-estimation by the above method in CaSO₄:Dy Teflon TLDS, is independent of the photon energy of the incident radiation in the range 30 keV - 1.25 MeV as well as of the irradiation history. Annealing at 240 ^oC was found to restore the original as well as the re-estimated TL sensitivity after a gamma dose of 0.12 Gy. This is unlike the case with PTTL technique in LiF. The above differences arise because in the first method, the re-estimated TL is still a characteristic of dosimetry traps whereas the PTTL is a characteristic of deep traps.

• Radiation Protection Dosimetry

Source: http://rpd.oxfordjournals.org/content/1/2/125 

1977 The re-estimation of absorbed doses with thermoluminescent dosemeters

Phys Med Biol. 1977 Jan;22(1):29-35.

The re-estimation of absorbed doses of less than 1 rad measured with lithium fluoride thermoluminescent dosemeters.

Mason EW, McKinlay AF, Saunders D.

Abstract

The technique of ultraviolet light bleaching for the re-estimation of the absorbed dose of radiation received by lithium fluoride thermoluminescence dosemeters has been extended to the extruded ribbon and PTFE disc form of dosemeter. The threshold of detection for the re-estimation of absorbed dose was found to be 1-1 rad for the PTFE disc dosemeters and 2-8 rad for the extruded ribbon dosemeters. A further study of this technique has revealed that by raising the temperature of the dosemeter during bleaching the threshold for re-estimated absorbed doses may be substantially reduced. The optimum temperature was found to be 80 degrees C and the practical threshold for the re-estimation of absorbed dose using a PTFE disc dosemeter was determined as 750 mrad.

PMID:

 

840895

 

[PubMed - indexed for MEDLINE]

PERSONAL ALPHA DOSIMETRY

The Radiation Safety Institute of Canada uses world-class, patented technology in our personal alpha dosimetry (PAD) service. There is simply no better system available in Canada for monitoring the radiation exposure of individual workers from radon and thoron progeny and from long-lived radioactive dust (LLRD). 

We’re pleased to announce that our Personal Alpha Dosimetry (PAD) license with the Canadian Nuclear Safety Commission (CNSC) has been renewed in June of 2012 for a 10 year period. 

The Radiation Safety Institute of Canada remains the only licensed dosimetry service in Canada for the measurement of radon progeny and long-lived radioactive dust (LLRD).

• A reliable, efficient and fully integrated personal radiation exposure monitoring system
• The PAD is lightweight, self-contained and durable – quite simply the most accurate and convenient technology available on the market
• Government certified and licensed by the Canadian Nuclear Safety Commission (CNSC)
• Best of all, every aspect of the Institute’s PAD system is backed by our world-class scientific and technical staff

Worker at Cameco Corporation's Rabbit Lake uranium mine wears a PAD while operating a remote control scoop tram. Photo courtesy of Cameco.

Originally developed in 1983, the Radiation Safety Institute of Canada’s Personal Alpha Dosimeter has become an indispensable safety tool for the uranium mining industry and companies involved in the clean-up of radioactive waste sites. In fact, our PAD service is the only licensed radiation dosimetry service in North America capable of measuring the actual exposure of individual workers to alpha radiation from radon and thoron progeny and LLRD.

How the PAD System works

The Radiation Safety Institute of Canada’s PAD system consists of a dosimeter head and an air sampling unit. The PAD is worn on a worker’s belt. At the end of each month, the dosimeter head is removed and replaced by a fresh head. The used head is sent to our National Laboratories in Saskatoon, Saskatchewan for processing. Transport of the used heads is easy, quick and efficient.

The PAD Service includes laboratory analysis, technical support, on-site equipment, quality assurance, quality control and timely reporting of results, including early alerts. Results are sent to clients and also sent to Health Canada’s National Dose Registry (NDR), as required.

Source: http://www.radiationsafety.ca/workplace/radiation-exposure-services/personal-alpha-dosimetry 

Medical Dosimetry Program

Welcome to the Medical Dosimetry Program at UW-L

What is Medical Dosimetry?  The field of Medical Dosimetry involves the measurement and calculation of dose for the treatment of cancer patients.  Dosimetrists use their knowledge of physics, anatomy, and radiobiology to develop an optimal arrangement of radiation portals to spare normal and radiosensitive tissues while applying a prescribed dose to the targeted disease volume.

UW-La Crosse sponsors the only Medical Dosimetry Program in the nation that offers online distance education for dosimetry students using the Desire2Learn E-learning course management system.

The Medical Dosimetry Program offers a 16 month certificate program as well as a Master of Science degree in medical dosimetry.  Both programs include clinical internships and online didactic coursework.

This web site informs prospective students about the program, the profession, and the unique possibilities associated with it.  Additionally, a wealth of information regarding admissions and application materials is also available here.  

Please contact the program via e-mail mdprogram@uwlax.edu with any questions or concerns you may have regarding the program.

Source: http://www.uwlax.edu/md/

Determinación de la dosis absorbidaen radioterapia con haces externos

Un Código de Práctica Internacional para la dosimetría basada en patrones de dosis absorbida en agua

Este Código de Práctica satisface la necesidad de un abordaje sistemático y unificado internacionalmente para la calibración de cámaras de ionización en términos de dosis absorbida en agua, y para la utilización de estos detectores en la determinación de la dosis absorbida en agua para haces de radiación utilizados en radioterapia. El Código de Práctica proporciona una metodología para la determinación de la dosis absorbida en agua haces de fotones de baja, media y alta energías, haces de electrones, haces de protones y haces de iones pesados empleados en radioterapia externa. 

Texto completo:

http://es.scribd.com/doc/55069251/11/La-red-OIEA-OMS-de-los-LSCD

Laboratorio Secundario de Calibración para Dosimetría en Niveles de Terapia en la Universidad de Santiago

F Gómez, D González-Castaño, A. Pazos


ESTÁNDAR PRIMARIO DE DOSIS ABSORBIDA EN AGUA DEL PTB:
Calorímetro de agua


Texto completo: http://www.sefm.es/userfiles/congreso-sevilla-mayo-2011/miercoles_11_mayo/sesion_a022/74.pdf

LABORATORIO DE REFERENCIA DE MEXICO PARA DOSIMETRIA DE RADIACIONES IONIZANTES

Víctor Tovar M., José Álvarez R., Víctor Pérez M O., Héctor Garnica G., Francisco Vergara


Resumen:
El Laboratorio Secundario  de Calibración Dosimétrica (LSCD) fue creado para proveer trazabilidad en las magnitudes y unidades empleadas en campos de radiaciones ionizantes para los equipos utilizados en centros de radioterapia, protección radiológica y radiología diagnóstica. Desarrollando y manteniendo los patrones de referencia para la dosimetría en haces de fotones y partículas cargadas. 

El LSCD pertenece a la red de laboratorios del Organismo Internacional de Energía Atómica OIEA y del Sistema Interamericano de Metrología SIM. En particular se  presentan la historia, desarrollo y actividades del LSCD  del Instituto Nacional de Investigaciones Nucleares (ININ) el cual ha sido acreditado ante el BIPM como el  laboratorio de referencia  en la República Mexicana en el área de radiaciones ionizantes para complementar las actividades del CENAM. 


Texto completo: http://www.cenam.mx/memsimp06/Trabajos%20Aceptados%20para%20CD/Posters/P-25.pdf

SERVICIOS DE DOSIMETRÍA EN MEXICO

Razón Social	Domicilio	Telefonos	Correo Electrónico
Asesoría Integral en Dosimetría Termoluminiscentes. S.A. de C.V.	Av. Canal de Miramontes No. 2030-14. Col. Educación. C.P. 04400 Coyoacán, D.F.	(55) 5336 1621 (55) 5336 1528	aidtsa@prodigy.net.mx
Asesoría Integral en Seguridad Radiológica	Manuel González No. 142 A-502 Col. Tlatelolco, Delegación Cuahutemoc, C.P. 06900 D.F.	(55) 5782 5296 Fax: (55) 5782 8589	asesoriaradiologica @hotmail.com
Asesores en Protección Radiológica y nuclear	Bordo No. 28-9 Col. Ejido Viejo Santa Ursula Coapa, Delegación Coyoacán C.P. 04850 D.F.	Tel/Fax:             (55) 5678 2223                   (55) 5679 6450	aspran@prodigy.net.mx
Alsa Dosimetría, S. de R.L. de C.V.	Sevilla No. 303, Col. Portales C.P. 03300 México, D.F.	Tel/Fax             (55) 5538 8690                   (55) 5519 7085                   (55) 5519 4288                   (55) 5519 2471	arsa@asesores enradiaciones.com.mx
Radiaciones y equipos de México, S.A. de C.V.	Plan de Ayutla 57-3 Col. San Lorenzo la Cebada, Delegación Xochimilco C.P. 16035, D.F.	Tel..    (55) 5555 8904       Tel Fax:             (55) 5555 8902	rademsa@avantel.net rademsa@yahoo.com.mx
Tecnofisica, S.A. de C.V.	Reforma Ote. No. 2220 Col Modelo C.P. 64580 Monterrey, N.L.	(81) 1052 0900       Fax (81) 4040 5173	info@tecnofisica.com.mx
Radiación y Dosimetría , S.A. de C.V.	David Pastrana Jaimes No. 34 Col. Constitución de 1917 Delegación Iztapalapa, C.P. 09260, D.F.	(55) 1546 3837 (55) 1546 4517	raddos@live.com.mx
Serida, S.A. de C.V.	Blvd. G. Salinas No. 1159-H, Col. Aviación, C.P. 22014 Tijuana, Baja California	(66) 4686 6576       Tel/Fax:             (66) 4686 6597	seri070907@prodigy.net.mx

• La presente tabla es de carácter informativo, la Comisión Nacional de Seguridad Nuclear y Salvaguardias, no recomienda a empresa, institución ó persona física alguna, ni se compromete por cualquier error u omisión en la presente tabla.
• Se recomienda que se solicite a las empresas, instituciones ó personas físicas indicadas en la relación, que presente su autorización original correspondiente, emitida por esta Comisión.
• Para cualquier duda o aclaración, favor de comunicarse con el Ing. Ignacio Jiménez Castro a los teléfonos 01(55) 5095 3200  Ext 222 ó 01(55) 5095 3272 directo, en el horario de 8:30 a 13:00 y de 14:30 a 17:00.

Última modificación Febrero 02, 2012 14:06:15