Plutonium Biokinetics in Human Body A. Luciani - Kit-Bibliothek - FZK

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The group of remainder organs is composed of the following ten additional tissues and organs: adrenals, brain, small intestine, upper large intestine, kidney, muscle, pancreas, spleen, thymus and uterus. It should be pointed out that the absorbed dose is a dosimetric quantity that is generally used in physics to express the energy absorbed in the matter, not necessarily organs and tissues, owing to the interaction of ionizing radiation. The equivalent dose and the effective dose are typically radiation protection quantities because they are corrected by dimensionless factors, the radiation and tissue weighting factors, in order to reflect the probability of occurrence of stochastic effects. The presented radiation protection quantities can be considered as an indicator of the risk associated to the exposition to ionizing radiations. In case of exposure from external radiation sources (external dosimetry) such quantities are evaluated by means of operational quantities connected to measurable quantities as the absorbed dose and fluxes. In case of internal dosimetry the radiation protection quantities are calculated by means of the biokinetics models. The dose is delivered to the organs and tissue for all the time the radionuclides is retained in the body, but for radiation protection purposes of professionally exposed workers a period of 50 years is considered. The radiation protection quantities used in internal dosimetry and calculated on a time period of 50 years are conventionally named as “committed”. The committed equivalent dose to a certain target organ T, due to the radionuclide retained in the organ source S, is expressed, according to ICRP methodology, as the product of two factors: • The total number of transformations of the radionuclide in the source organ; • the energy absorbed per grams in the target organ per transformation of the radionuclide in the source organ . Therefore the committed equivalent dose is given by: H(50)(T← S) = kU S 158 SEE(T← S) R equation A.6 where: U S is the number of nuclear transformations of the radionuclide in source organ S over a conventional period of 50 years; SEE(T
w R is the radiation weighting factor for the radiation type R; m T (in grams) is the mass of the target organ T. The total committed equivalent dose to the target organ T from all the source organs S, over which the introduced radionuclide is distributed, is given by the summation over source organs S: ∑ = k∑U S∑ SEE(T← S) R = k∑ US S R S R H T (50) = H(50)(T←S) S 159 Y R E Rw R AF(T ← S) R m T equation A.8 The committed effective dose is calculated on the basis of the committed equivalent dose analogously to the expression in equation A.4: E(50)= ∑wTHT(50) T equation A.9 The ICRP, in the Publication 61, provides an expression to evaluate the committed effective dose where a way to weight committed equivalent dose for the organs or tissues of the remainder group is also given: 12 ∑ E(50) = wT HT (50) + wremainder T = 1 equation A.10 where T ranging from 1 to 12 represents the main organs of Table A.2, T ranging from 13 to 22 represents the ten remainder organs with tissue weighting factor w remainder = 0.05 and m T is the respective mass. In those exceptional cases in which a single one of the remainder tissues or organs receives an equivalent dose in excess of the highest dose absorbed by any of the twelve main organs or tissues for which a weighting factor is specified (Table A.2), half of w remainder (0.025) must be applied to this tissue or organ and half of w remainder to the average dose in the rest of the remainder organs group. Therefore in such case the committed effective dose must be calculated as: 12 ∑ E(50) = wT HT (50) + 0.025 T = 1 22 ∑ T =13 equation A.11 where T* relates to the organ or tissue of the remainder group that has the highest committed equivalent dose in comparison to the main organs or tissues. 22 ∑ ∑ m T H T (50) T =13 22 ∑ mT T = 13 mT HT (50) − mT*HT*(50) 22 m − m T T* + 0.025HT*(50) ∑ T=13
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Forschungszentrum Karlsruhe in der
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Für diesen Bericht behalten wir un
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i ABSTRACT The biokinetic model pre
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ZUSAMMENFASSUNG Das von der Interna
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1 INDEX OF CONTENTS INDEX OF SYMBOL
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3 INDEX OF SYMBOLS Here a short glo
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Chapter 1 Introduction 5
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the duties of the Department for Ra
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adionuclide. Therefore only isotope
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stabilise the +4 oxidation state [1
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techniques adopted in the early pha
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present in spent and MOX reactor fu
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INTRAVENOUS INJECTION skin WOUND bl
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functions, defined as retained and
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the contamination event, of such as
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Table 1.3.2 Indicative 239 Pu detec
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The kinetics of Plutonium in the ki
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1.4.2 COMMENTS ON THE ICRP 67 MODEL
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Chapter 2 Data and measurements 31
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Therefore the radiolysis process, m
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Recent technologic developments in
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eu(t) = 0.19e −0.272t + 0.023e
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function for each of the considered
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the minimum detectable activity of
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2.2.2 AVAILABLE MEASUREMENTS Immedi
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Table 2.2.4 Daily fecal excretion o
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elements the spectral distribution
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The phoswich detector is based on t
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HPGe crystals are produced in cylin
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This quantity is normally expressed
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The peak is located in the region B
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To introduce the second quantity, t
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117 cm 3 h -1 for the incoming and
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Figure 2.3.8 The Lawrence Livermore
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three detectors are used. Two detec
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Table 2.3.4 Efficiency factors of p
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• the necessity of performing mea
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Table 2.3.7 Impulses in the measure
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2.4 ACTIVITY MEASUREMENTS IN BIOASS
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If more then one radionuclide is ma
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L A is the air layer in µgcm -2 ;
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The electrodeposition cell used for
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Table 2.4.1 238 Pu, 239 Pu and 241
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3.1.1 MATHEMATICAL TOOLS 3.1.1.1 So
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calculating the amount of Plutonium
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3.1.2 ANALYSIS OF THE ICRP 67 MODEL
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empirical curves given by Langham,
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the worst performance of the group.
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leave the total clearance from the
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Figure 3.1.4 shows that the use of
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3.1.3 MODIFICATION OF ICRP 67 MODEL
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The structure of Polig’s skeleton
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Percentage daily urinary excretion
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of 0.693d -1 . The values of the F
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Percentage daily urinary excretion
Page 117 and 118: the basis of all the reference data
Page 119 and 120: Table 3.1.10 Transfer rates of the
Page 121 and 122: 3.1.4 VERIFICATION OF THE OPTIMIZED
Page 123 and 124: Table 3.1.13 Intakes and percentage
Page 125 and 126: soft tissue ST2 soft tissue ST0 sof
Page 127 and 128: For the routine application of Mode
Page 129 and 130: excreted by individuals aged sixty
Page 131 and 132: Table 3.1.20 Exponents and coeffici
Page 133 and 134: tract [57] to consider a contaminat
Page 135 and 136: The sensitivity coefficients for th
Page 137 and 138: Sensitivity coefficients S i Figure
Page 139 and 140: transfer rates on the Plutonium uri
Page 141 and 142: Geometric standard deviations rangi
Page 143 and 144: Percentage daily urinary excretion
Page 145 and 146: Percentage daily urinary excretion
Page 147 and 148: 3.2 APPLICATION OF THE OPTIMIZED MO
Page 149 and 150: lymph nodes, as in the LLNL phantom
Page 151 and 152: Americium in the lungs [Bq] 1000 10
Page 153 and 154: Daily urinary excretion [Bqd -1 ] 1
Page 155 and 156: long time is not yet described by t
Page 157 and 158: excretion that is one of the main i
Page 159 and 160: The comparison of model’s predict
Page 161 and 162: Americium in the lungs [Bq] 1000 10
Page 163 and 164: 153 CONCLUSIONS The optimized model
Page 165 and 166: Annex Quantities used in Radiologic
Page 167: present. As the radiation weighting
Page 171 and 172: 161 BIBLIOGRAPHY 1. Plutonium. W. K
Page 173 and 174: 29. Nenot, J.-C. and Stather, J. W.
Page 175 and 176: 55. International Atomic Energy Age
Page 177 and 178: 81. Crowley, J., Lanz, H., Scott, K
Page 179 and 180: 107. Hempelmann, L.H., Langham,W.H.
Page 181 and 182: 137. Breitestein, B.D., Newton, C.E
Page 183 and 184: 167. Harrison, J.D., Khursheed, A.,
Page 185 and 186: JOURNALS OWN PUBLICATIONS RELATED T
Page 187 and 188: 177 ACKNOWLEDGEMENTS Special thanks
Page 189 and 190: Name: Andrea Luciani Date and place
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Plutonium Biokinetics in Human Body A. Luciani - Kit-Bibliothek - FZK

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