Determination of the Fricke G value for HDR 192Ir sources using ionometric measurements
Creators
- 1. Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil). Lab. de Ciencias Radiologicas
- 2. Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil)
Description
High Dose Rate (HDR) brachytherapy using 192Ir is widely accepted as an important treatment option, and it thus requires an accurate dosimetry standard. However, a dosimetry standard for the direct measurement of absolute dose to water is currently not available. The dose to water conversion is calculated via the dose rate constant Λ and several correction factors accounting for the scatter, attenuation, and anisotropy of the dose distribution, among other effects. Two potentially useful procedures have been reported, including one by Sarfehnia et al. [3,4], which used a water-based calorimeter with an uncertainty of 1.9% for k=1, and a second by Austerlitz et al. and de Almeida et al., which used Fricke dosimetry with estimated uncertainties of 3.9% for k=1 and 1.4% for k=1, respectively. Chemical dosimetry using a standard FeSO4 solution has shown potential to be a reliable standard of absorbed dose for the HDR 192Ir source. A major uncertainty is associated with the G values reported by Fregene, which had a numerical value of 1.1 %. However, that reference provided very little detail of the experimental procedures for the 192Ir source. The G value may be obtained by using a calorimeter or ionometric measurements. In the absence of calorimetric data, this paper makes an attempt to measure the G value for the HDR 192Ir sources using ionometric measurements and recommendations from dosimetry protocols. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-BR--10528
Conference
- Title
- International nuclear atlantic conference. Nuclear energy: new jobs for a better life; 17. ENFIR: Meeting on nuclear reactor physics and thermal hydraulics; 10. ENAN: Meeting on nuclear applications; 2. ENIN: Meeting on nuclear industry
- Acronym
- INAC 2011
- Dates
- 24-28 Oct 2011
- Place
- Belo Horizonte, MG (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 42109363
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRACHYTHERAPY; CHEMICAL DOSEMETERS; CHEMICAL RADIATION DETECTORS; DOSE RATES; INTERNAL IRRADIATION; IRIDIUM; IRIDIUM 192; IRRADIATION; RADIATION DOSE DISTRIBUTIONS; RADIATION SOURCE IMPLANTS; RADIOPHARMACEUTICALS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DAYS LIVING RADIOISOTOPES; DOSEMETERS; DRUGS; ELECTRON CAPTURE RADIOISOTOPES; ELEMENTS; HEAVY NUCLEI; IMPLANTS; INTERNAL CONVERSION RADIOISOTOPES; IRIDIUM ISOTOPES; IRRADIATION; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; LABELLED COMPOUNDS; MATERIALS; MEASURING INSTRUMENTS; MEDICINE; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR MEDICINE; NUCLEI; ODD-ODD NUCLEI; PLATINUM METALS; RADIATION DETECTORS; RADIATION SOURCES; RADIOACTIVE MATERIALS; RADIOISOTOPES; RADIOLOGY; RADIOTHERAPY; REFRACTORY METALS; THERAPY; TRANSITION ELEMENTS; YEARS LIVING RADIOISOTOPES