187:
each compartment is called
Initial Deposition Fraction or IDF. It is a function of Activity Median Aerodynamic Diameter (AMAD), which includes size, shape, density, anatomical and physiological parameters as well as various conditions of exposure. The IDF values may be calculated either following the procedure described in ICRP 130/66 or obtaining it from their Annex. The general model of the HRTM is common to any element except the absorption rates {fr, ss, sr} which are related to the chemical form of the element. ICRP gives default values of absorption rates according to types F, M or S, but specific value for some compounds are available in ICRP 134 and ICRP 137.
186:
This model is applied for modeling the intake of radioactive aerosols by inhalation. The detailed description is given in ICRP 130 (2016) updating the ICRP 66 (1994). If a person inhales instantaneously a quantity I, it is deposited directly in some compartments of the HRTM. The fraction deposited in
194:
This is applied for modeling the intake of particles in the GI tract following the model provided ICRP 105 (ICRP 2005). Particles can be introduced in the GI Tract directly by ingestion, or from the RT. Deposition is in the stomach (ST). Part or all the flow is transferred, through SI, to the blood
87:
The ICRP further states "For internal exposure, committed effective doses are generally determined from an assessment of the intakes of radionuclides from bioassay measurements or other quantities (e.g., activity retained in the body or in daily excreta). The radiation dose is determined from the
175:
The ICRP models are used to simulate the distribution of the isotopes inside the human being. All current ICRP models, compiled in the OIR (ICRP134/137) data viewer, can be represented by compartmental systems with constant coefficients. The conceptual model used by ICRP can be summarized as it
202:
They are specific compartments to be applied for an element. Current models are described in ICRP 134 and ICRP 137. A few computer codes have been developed to estimate intake and calculate internal dose using biassay data.
130:
Internal dose monitoring of the radionuclides which emit radiation which can penetrate out of the body. For example X-rays, gamma rays of sufficient energy. It can be measured by devices such as a whole body counter.
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In a radioactive area, radionuclide particulate may be suspended in the air and can enter the body by inhalation. These particulates may be deposited in different parts of the respiratory tract depending upon their
248:
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48:(ICRP) biokinetic models are applied to establish a relationship between the individual intake and the bioassay measurements, and then to infer the internal dose.
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Monitoring of the radionuclides present in the body using the bio-assay sample taken out of the body; this includes samples of urine, sweat, feces, etc.
45:
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155:, LLNL, JAERI, thyroid and the knee phantoms. Some of the renowned mathematical phantoms are MIRD, CRISTY and nowadays voxel phantoms also known as
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is the integration time in years following the intake. The commitment period is taken to be 50 years for adults, and to age 70 years for children.
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data. Computer programs can be used for bioassay evaluations. The bioassay measurement values can be used to estimate unknown intake.
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Phoswich detectors with Be window and thin NaI(Tl)crystal and thick CsI(Tl)or CsI(Na), for low energy (<100 keV) photon detection
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Calibration of these systems is carried out with different type of physical and mathematical phantoms. Physical phantoms include
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The internal doses for workers or members of the public exposed to the intake of radioactive particulates can be estimated using
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HPGe detectors are replacing detectors for measuring the low energy and high energy photons with appropriate electronic systems.
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73:) as the sum of the products of the committed organ or tissue equivalent doses and the appropriate tissue weighting factors
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195:(B). The rate transfer from SI to B, is given by fA. The value of fA is associated to the element and their chemical form.
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232:- the measure of health effect due to low radiation doses. Also contains a description of the various dose quantities.
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The internal radiation dose due to injection, ingestion or inhalation radioactive substances is known as
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data such as lung and body counter measurements, urine or faecal radioisotope concentration, etc. The
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Radionuclides deposited within a body will irradiate tissues and organs and give rise to
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IRPA paper 54302 - Internal
Dosimetry: The science and art of internal dose assessment
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International
Commission on Radiological Protection. OIR Data Viewer; 2018-07-15.
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until they are excreted from the body or the radionuclide is completely decayed.
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Optimal design and mathematical model applied to establish bioassay programs
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Biokinetic modeling is widely used in internal dosimetry and to evaluate
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There are a few routes of intake (of radionuclide) namely,
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has a low background arrangement with counting systems
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International
Commission on Radiological Protection
142:NaI(Tl) detectors for high energy photon detection
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88:intake using recommended dose coefficients".
69:The ICRP defines Committed effective dose, E(
545:Airborne radioactive particulate monitoring
16:Internal ionising radiation dose assessment
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309:G. Sanchez Health Phys. 92(1):64–72(2007)
184:The human respiratory tract model (HRTM).
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192:The Human Alimentary Tract Model (HATM).
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268:ICRP publication 103 - Paragraph 144.
710:Radiation Protection Convention, 1960
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30:incorporated inside the human body.
321:"Bioassay evaluations with Biokmod"
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22:is the science and art of internal
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477:Computed tomography dose index
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742:See also the categories
731:Radiation-induced cancer
726:Acute radiation syndrome
26:dose assessment due to
582:Semiconductor detector
538:measurement techniques
200:Systemic compartments.
601:Protection techniques
565:Scintillation counter
289:Whole Body Monitoring
122:Monitoring techniques
790:Radiation protection
760:Radiation protection
577:Radiation monitoring
570:Proportional counter
455:quantities and units
409:Background radiation
395:Radiation protection
278:Aerodynamic diameter
207:Bioassay evaluations
171:Biokinetic modelling
116:aerodynamic diameter
592:Whole-body counting
502:Mean glandular dose
439:Radioactive sources
163:In-vitro monitoring
429:Internal dosimetry
424:Ionizing radiation
136:whole body counter
127:In-vivo monitoring
24:ionising radiation
20:Internal dosimetry
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748:Radiation effects
719:Radiation effects
482:Counts per minute
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58:committed dose
56:Main article:
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52:Committed dose
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35:committed dose
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756:Radiobiology
587:Survey meter
507:Monitor unit
453:Measurement
444:Radiobiology
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359:ICRP website
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329:. Retrieved
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628:Respirators
560:Ion chamber
774:Categories
688:Regulation
331:2016-12-13
237:References
109:Absorption
100:Inhalation
700:NRC (USA)
649:HPS (USA)
550:Dosimeter
467:Becquerel
414:Dosimetry
176:follows.
106:Injection
103:Ingestion
705:ONR (UK)
695:IRR (UK)
674:SRP (UK)
613:Glovebox
517:Roentgen
219:See also
213:bioassay
80:, where
42:bioassay
679:UNSCEAR
644:Euratom
527:Sievert
230:Sievert
758:, and
153:BOMAB
669:IRPA
664:ICRP
659:ICRU
654:IAEA
497:Gray
522:Rem
512:Rad
198:c)
190:b)
182:a)
776::
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159:.
134:A
118:.
66:.
387:e
380:t
373:v
334:.
82:t
78:T
75:W
71:t
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