Application of the Böhm chamber for reference beta dose measurements and the calibration of personal dosimeters

• Autorzy: Skubacz K.

Identyfikatory

DOI

10.1515/nuka-2016-0001

• Języki publikacji: EN

Abstrakty

EN

Thermoluminescent dosimeters (TLDs) currently used in personal and area dosimetry are often utilized to measure doses of ionizing radiation in fields with a more complex structure and therefore they should be calibrated in relation to different radiation types. The results of such calibration presented for UD-813 TLDs allowed for evaluation of their capability in relation to different radiation types like the beta and photon radiation of different energies and neutron radiation generated by the 241Am-Be source. The detector response for 60 keV photons was 10% higher than for the 662 keV gamma radiation of 137Cs. There were also response differences in relation to photon and beta radiation between detectors with an enhanced concentration of lithium 6Li and boron 10B and detectors containing a natural level of these isotopes. Measurements of the reference beta doses were performed with the help of the Böhm chamber. This method is relatively more complicated compared to determining the reference photon and neutron doses and is described thoroughly in this paper. The corrected current measured by the Böhm chamber for the chosen parameters was a linear function for an entire available range of the chamber depths. The percentage of errors related to the evaluated reference beta doses were below 2% despite a rather large number of corrections that should be taken into account. The calibration distances varied from 11 cm to 50 cm. For this range and beta particle energy, the absorption of radiation in the air was negligible and their attenuation had a predominantly geometric character.

Słowa kluczowe

EN

beta radiation; Böhm chamber; mixed fields; Panasonic TLDs

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2016
• Tom: Vol. 61, No. 1
• Strony: 61--67
• Opis fizyczny: Bibliogr. 12 poz., rys.

Twórcy

autor

Skubacz K.

• Silesian Centre for Environmental Radioactivity (BCR), Central Mining Institute, 1 Gwarków Sq., 40-166 Katowice, Poland, Tel.: [phone], Fax: [phone]

Bibliografia

• 1. Skubacz, K. (2015). Measurements of low doses with Panasonic dosimeters. Algorithm and tests. Radiat. Meas., 75, 9–14. DOI: 10.1016/j.radmeas.2015.02.020.
• 2. International Organization for Standardization. (1996). X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy – Part 1: Radiation characteristics and production methods. ISO 4037-1-1996. Geneva.
• 3. Piesch, E., & Burgkhardt, B. (1988a). Albedo dosimetry system for routine personnel monitoring. Radiat. Prot. Dosim., 23(1/4), 117–120.
• 4. Olko, P., Currivan, L., Van Dijk, J. W. E., Lopez, M. A., & Wernli, C. (2006). Thermoluminescence detectorsapplied in individual monitoring of radiation workers in Europe – a review based on the EURADOS questionnaire. Radiat. Prot. Dosim., 120(1/4), 298–302.DOI: 10.1093/rpd/nci538.
• 5. Rivera, T. (2012). Thermoluminescence in medical dosimetry. Appl. Radiat. Isot., 71, 30–34. DOI: 10.1016/j.apradiso.2012.04.018.
• 6. Piesch, E., & Burgkhardt, B. (1988b). Field calibration technique for albedo neutron dosemeters. Radiat. Prot. Dosim., 23(1/4), 121–126.
• 7. Olko, P. (2010). Advantages and disadvantages of luminescence dosimetry. Radiat. Meas., 45(3/6), 506–511. DOI: 10.1016/j.radmeas.2010.01.016.
• 8. Budzanowski, M., & Burgkhardt, B. (1995). Thin 6/7LiF’Mg,Cu,P and 6/7LiF:Mg,Ti detectors for automatic albedo neutron dosimetry. Radiat. Meas., 24(4), 445–448. DOI: 10.1016/1350-4487(95)00015-7.
• 9. International Organization for Standardization. (2004). Nuclear energy – Reference beta-particle radiation – Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field. ISO 6980-2:2004. Geneva.
• 10. International Commission on Radiation Units and Measurements. (1998). Conversion coefficients for use in radiological protection against external radiation. Bethesda: ICRU. (Report 57).
• 11. Böhm, J. (1986). The national primary standard of the PTB for realizing the unit of the absorbed dose rate to tissue for beta radiation. Braunschweig: Physikalish Technische Bundesanstalt. (PTB-Dos-13).
• 12. Urban, P., & Skubacz, K. (2013). Large-scale system for dosimetric measurements in industry and medicine. Zeszyty Naukowe WSZOP, 1(9), 68–82.

Uwagi

PL

Opracowanie ze środków MNiSW w ramach umowy 812/P-DUN/2016 na działalność upowszechniającą naukę.