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

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present in spent and MOX reactor fuel. The remaining 28 % of Plutonium comes from military applications. As to the Plutonium from spent fuel, more recent data gave a worldwide production of 75 tons in 1997. It is estimated that the annual production figure will remain more or less the same until 2010. The cumulative amount of Plutonium in spent fuel from nuclear power reactors worldwide is predicted to increase to about 1700 tons by 2010 [46]. In the last years increasing amounts of Plutonium are expected to be removed from military programs, owing to the dismantling of thousands of US and Russian warheads on the basis of the START-I and START-II treaties. At least 50 tons of Plutonium from each side are expected. Table 1.2.2 Estimates for inventories of Plutonium at the end of 1990. Civilian sources Total in spent and MOX reactor fuel separated in store in fast reactor fuel Military sources Total in warheads Application Tonnes weapon-grade outside warheads others Besides the application based on controlled (civilian) and explosive (military) fission reactions, Plutonium has been widely used as a thermo-electric generator: By means of thermoelectric couples, the heat produced by the nuclear decays is converted into electric power and used to supply energy to low-power control and communication equipment. This kind of power source has many advantages such as lightness and compactness (to fit within a spacecraft), resistance to ambient conditions (low temperatures, radiation and meteorites) and independence from sunlight (permitting explorations of distant planets). For such purposes 238 Pu has been widely used, because its high energy alpha particles (5.499 Mev) and the relatively short half-life (87.74 y) result in a high specific activity (6.34•10 11 Bqg -1 ) and a favorable power to weight ratio, quoted to be 0.57 Wg -1 [47]. 16 545 72 37 654 178 56 23 257
1.3.1 PATHS AND MODES OF INTAKE 1.3 PRINCIPLES OF INTERNAL DOSIMETRY In the human body different radioisotopes are commonly present as a consequence of the dietary intake and respiratory exchanges (Table 1.3.1). The most common natural radionuclides are: 3 H, 7 Be and 14 C originating from cosmic ray interactions with the terrestrial atmosphere; 40 K, 87 Rb and 138 La since primordial ages in the lithosphere; the natural series of 238 U, 235 U and 232 Th with their progenies [49]. Additional radionuclides come from the global fallout following the numerous atomic weapon tests in the atmosphere carried out in the sixties and seventies. All of these radionuclides and others of minor importance are introduced into the body in relation to the environmental and geological conditions of the area where the subjects are used to live and to its dietary habits. Activities of radionuclides normally present in adult human subjects are given in [50]. Human technologies which involve the use of radioactive materials, such as nuclear power and related procedures (mining, transports, fuel production and reprocessing, waste management), applications in the conventional industries, scientific research, medical applications, etc. can be a source of additional exposure for the population and the workers involved. Table 1.3.1 Indicative values of human body content of main natural radioisotopes. Radionuclides Amount [Bq] Origin 3 H 14 C 40 K 87 Rb 226 Ra 228 Ra 214 Pb, 214 Bi 235,238 U 137 Cs 90 Sr- 90 Y 239,240 Pu 30 10 2 - 10 3 4 – 5 • 10 3 700 1 - 10 0.4 40 1.5 100 30 0.4 17 global fallout and natural “ natural “ “ “ “ “ global fallout Substances can enter the human body through essentially five pathways: Inhalation, ingestion, injection, wound and absorption through skin. The quantity of activity entering the body is conventionally named intake. The phase of the contamination in which the activity is not yet absorbed into fluids (as in the early phases of inhalation or ingestion) is named presystemic phase. A scheme of the possible paths of intake with a general overview of the main transfers in the body is presented in Figure 1.3.1 (modified from [51]). “ “
Page 1: Forschungszentrum Karlsruhe in der
Page 4 and 5: Für diesen Bericht behalten wir un
Page 7 and 8: i ABSTRACT The biokinetic model pre
Page 9 and 10: ZUSAMMENFASSUNG Das von der Interna
Page 11 and 12: 1 INDEX OF CONTENTS INDEX OF SYMBOL
Page 13 and 14: 3 INDEX OF SYMBOLS Here a short glo
Page 15: Chapter 1 Introduction 5
Page 18 and 19: the duties of the Department for Ra
Page 20 and 21: adionuclide. Therefore only isotope
Page 22 and 23: stabilise the +4 oxidation state [1
Page 24 and 25: techniques adopted in the early pha
Page 28 and 29: INTRAVENOUS INJECTION skin WOUND bl
Page 30 and 31: functions, defined as retained and
Page 32 and 33: the contamination event, of such as
Page 34 and 35: Table 1.3.2 Indicative 239 Pu detec
Page 36 and 37: The kinetics of Plutonium in the ki
Page 38 and 39: 1.4.2 COMMENTS ON THE ICRP 67 MODEL
Page 41: Chapter 2 Data and measurements 31
Page 44 and 45: Therefore the radiolysis process, m
Page 46 and 47: Recent technologic developments in
Page 48 and 49: eu(t) = 0.19e −0.272t + 0.023e
Page 50 and 51: function for each of the considered
Page 52 and 53: the minimum detectable activity of
Page 54 and 55: 2.2.2 AVAILABLE MEASUREMENTS Immedi
Page 56 and 57: Table 2.2.4 Daily fecal excretion o
Page 58 and 59: elements the spectral distribution
Page 60 and 61: The phoswich detector is based on t
Page 62 and 63: HPGe crystals are produced in cylin
Page 64 and 65: This quantity is normally expressed
Page 66 and 67: The peak is located in the region B
Page 68 and 69: To introduce the second quantity, t
Page 70 and 71: 117 cm 3 h -1 for the incoming and
Page 72 and 73: Figure 2.3.8 The Lawrence Livermore
Page 74 and 75: 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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the basis of all the reference data
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Table 3.1.10 Transfer rates of the
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3.1.4 VERIFICATION OF THE OPTIMIZED
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Table 3.1.13 Intakes and percentage
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soft tissue ST2 soft tissue ST0 sof
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For the routine application of Mode
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excreted by individuals aged sixty
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Table 3.1.20 Exponents and coeffici
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tract [57] to consider a contaminat
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The sensitivity coefficients for th
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Sensitivity coefficients S i Figure
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transfer rates on the Plutonium uri
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Geometric standard deviations rangi
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3.2 APPLICATION OF THE OPTIMIZED MO
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lymph nodes, as in the LLNL phantom
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Americium in the lungs [Bq] 1000 10
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Daily urinary excretion [Bqd -1 ] 1
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long time is not yet described by t
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excretion that is one of the main i
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The comparison of model’s predict
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Americium in the lungs [Bq] 1000 10
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153 CONCLUSIONS The optimized model
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Annex Quantities used in Radiologic
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present. As the radiation weighting
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w R is the radiation weighting fact
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161 BIBLIOGRAPHY 1. Plutonium. W. K
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29. Nenot, J.-C. and Stather, J. W.
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55. International Atomic Energy Age
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81. Crowley, J., Lanz, H., Scott, K
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107. Hempelmann, L.H., Langham,W.H.
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137. Breitestein, B.D., Newton, C.E
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167. Harrison, J.D., Khursheed, A.,
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JOURNALS OWN PUBLICATIONS RELATED T
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177 ACKNOWLEDGEMENTS Special thanks
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Name: Andrea Luciani Date and place
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Plutonium Biokinetics in Human Body A. Luciani - Kit-Bibliothek - FZK

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