Air kerma rate constants for radionuclides

Wasserman, Herman; Groenewald, Wilhelm

doi:10.1007/bf00286779

Cited by 23 publications

(17 citation statements)

References 1 publication

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“…where Γ 131I =56.1 μSvm 2 GBq −1 h is the specific gamma radiation constant for 131 I (Wasserman and Groenewald 1988); A is the 131 I activity in Bq of the daily dry sewage sludge produced; F is the yearly exposure time for the worker; and d is the distance in meters between the radioactive source (i.e., the sludge container) and the worker. Given an average daily production of 22,300 kg of dry sludge during the sampling period and a mean concentration of 323 Bqkg −1 of 131 I, we calculate A to be 7.2 MBq.…”

Section: Assessment Of Radiation Exposurementioning

confidence: 99%

Levels of 131I and Six Natural Radionuclides in Sludge from the Sewage Treatment Plant of Valladolid, Spain

Jiménez

Debán

Pardo

et al. 2010

Water Air Soil Pollut

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The levels of 131 I and six natural radionuclides ( 238 U, 226 Ra, 210 Pb, 228 Ra, 224 Ra, and 40 K) were determined in sewage sludge samples obtained from an urban wastewater treatment plant that services a medium-sized town in Spain. Secondary treatment of wastewater consisting of anaerobic, anoxic, and oxic stages is collectively called A2O processing. Radio analytical determinations were performed by gamma spectrometry using a highpurity germanium detector. This technique has proven useful in identifying local radioactive pollution. This type of pollution was consistently detected throughout the year, with several increases associated with authorized discharges from hospitals. Finally, we examined the radiation dose that workers are exposed to due to the presence of 131 I in the sludge. We found inhalation risk to be negligible, with external radiation as the main source of exposure to 131 I.

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Section: Assessment Of Radiation Exposurementioning

confidence: 99%

Levels of 131I and Six Natural Radionuclides in Sludge from the Sewage Treatment Plant of Valladolid, Spain

Jiménez

Debán

Pardo

et al. 2010

Water Air Soil Pollut

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“…T he conversion betwee n activity and dose rate is gi ven by *, t he specific dose constant. * for I-131 has been measured 17 The RPH e xternal dose rates we re m easured at waist height, 3 m from the patient, using one of two calibrate d survey m eters (Sm artIon 2120s or Inovision 451b). Both meters provide measurements of am bient dose e quivalent H*(10) in mSv, which is equivalent to the dose delivered to a depth of 10 mm in the "ICRU s phere phantom" 18 .…”

Section: Specific Dose Constantmentioning

confidence: 99%

Radiation protection recommendations for I-131 thyrotoxicosis, thyroid cancer and phaeochromocytoma patients

Woodings

2004

Australas Phys Eng Sci Med

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Iodine-131 patients pose a radiation risk to their family members, carers and colleagues. Doses from thyrotoxicosis and thyroid cancer patients undergoing standard treatments have been well characterised in the literature. However the resulting precautions cannot be easily adapted to circumstances where the patient has an unusual affliction, or an atypical family or occupational environment. In this study, a model for calculating dose from an I-131 patient is derived from first principles. The model is combined with existing results from the literature to determine a distance weighting factor between patients and family members. This technique reduces the uncertainty in the dose calculations by removing the need to guess the unknown patterns of close contact, a problem common to all previous dose calculation techniques. Data is presented for four unusual I-131 treatments; a child thyroid cancer patient, two thyroid cancer dialysis patients and a phaeochromocytoma patient. The model is used to calculate appropriate periods of restricted contact for these patients. The recommendations provide a useful guide for future unusual I-131 treatments.

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“…The sources used are listed in Cs sources are calibrated in air kerma, the uncertainty on the activity for these sources is a combination of the uncertainty on the declared air kerma value and the conversion coefficient, 13 which was set to 2.0%. …”

Section: Measurements With Point Bare Sourcesmentioning

confidence: 99%

Experiments and Monte Carlo modeling of a higher resolution Cadmium Zinc Telluride detector for safeguards applications

Borella

2016

Int. J. Mod. Phys. Conf. Ser.

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The Belgian Nuclear Research Centre is engaged in R&D activity in the field of Non Destructive Analysis on nuclear materials, with focus on spent fuel characterization. A 500 mm 3 Cadmium Zinc Telluride (CZT) with enhanced resolution was recently purchased. With a full width at half maximum of 1.3% at 662 keV, the detector is very promising in view of its use for applications such as determination of uranium enrichment and plutonium isotopic composition, as well as measurement on spent fuel. In this paper, I report about the work done with such a detector in terms of its characterization. The detector energy calibration, peak shape and efficiency were determined from experimental data. The data included measurements with calibrated sources, both in a bare and in a shielded environment. In addition, Monte Carlo calculations with the MCNPX code were carried out and benchmarked with experiments.

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Air kerma rate constants for radionuclides

Cited by 23 publications

References 1 publication

Levels of 131I and Six Natural Radionuclides in Sludge from the Sewage Treatment Plant of Valladolid, Spain

Levels of 131I and Six Natural Radionuclides in Sludge from the Sewage Treatment Plant of Valladolid, Spain

Radiation protection recommendations for I-131 thyrotoxicosis, thyroid cancer and phaeochromocytoma patients

Experiments and Monte Carlo modeling of a higher resolution Cadmium Zinc Telluride detector for safeguards applications

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