Interaction of Ionizing Radiation with Matter
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1 Interaction of Ionizing Radiation with Matter Interaction of neutrons with matter Neutral particles, no repulsion with the positively charged nucleus: important projectile Origin of the neutrons: Nuclear reactor Neutron source Neutrons must be moderated Moderators: water, hydrogen, deuterium 9 Be + α 12 C+ n 9 Be Am 12 C+ n 1
2 Interaction of Ionizing Radiation with Matter Interaction of neutrons with matter Neutral particles, no repulsion with the positively charged nucleus: important projectile Slow (moderated) neutrons react with many nuclei: Neutron capturing (n,γ) reactions Radioactive isotopes of almost all elements can be produced this way 2
3 Interaction of Ionizing Radiation with Matter Interaction of neutrons with matter Cross-section / barn Neutron energy / ev Cross section is a measure for the probability of a nuclear reaction (barn = m 2 ) 3
4 Interaction of Ionizing Radiation with Matter Neutron activation Non-destructive analytical method for trace analysis Suitable for qualitative & quantitative analyses (internal standard) λ N =Φ σ N T (1 e λt ) λ= decay constant of the daughter N = number of daughter atoms φ= fluence rate of neutrons σ= cross section N T = number of target atoms 4
5 Interaction of radiation with a biological system leads to an energy transfer The biological impact depends on: type of radiation type of irradiated biological material How to quantify the amount of transferred energy? How to quantify the biological impact? 5
6 Ion dose (exposure) I = produced charges mass of irradiated air I = Q m Radiation source SI Unit: I = C(As) kg = 6, Ion pairs kg air Ionization chamber Old unit: R (Roentgen) 4 2,58 10 C 1R = kg air C 1 kg air = 3, R Measurement of the ionization in an ionization chamber Gas filled container with a window of thin material Electric current is produced by ions which are produced by the influence of radiation 6
7 Energy dose absorbed radiation energy D = D = mass ΔW Δm the formation of 1 ion pair requires 34 ev SI unit: 1 Gy (Gray) 1 Gy = 1 J/kg Old unit: rd (rad) 1rd = 10-2 Gy Direct information about the transferred energy 7
8 Equivalent dose Damage of organic material (tissue) can only be expected if the energy is absorbed by the tissue (interactions radiation-matter) The bigger the absorption is, the bigger is the impact Highly ionizing radiation has a higher impact than weakly ionizing (α > n > β, γ, X) Energy dose exclusively reflects the pure energy value (not the impact) Equivalent dose H = D W W = weighting factor of the radiation SI Unit: 1 Sv (Sievert) 1 Sv = 1 J/kg old unit:1 rem 1 Sv = 100 rem (roentgen equivalent men) 8
9 Equivalent dose Representing the stochastic health effects of ionizing radiation on the human body. Equivalent Dose enables the comparison of different types of radiation. Equivalent dose H = D W W = weighting factor of the radiation normal cell damaged cell Radiation types X-rays, γ- and ß- radiation W Neutron radiation about 10 α - radiation 20 1 Biological sample after irradiation with β-particles Biological sample after irradiation with α-particles Dose rate: dh (Sv / h) dt relative destruction: 1 Energy dose: 2 Gy relative destruction: 1 Energy dose: 0.1 Gy 9
10 Dosimetry Ion dose measurable value Energy dose Information about the absorbed energy Equivalent dose Information about the biological impact Multiplication with the w factor of the particular material Multiplication with the weighting factor of the particular radiation 10
11 instantaneous physical process energy transfer Radiobiological functional chain minutes molecular & biochemical changes hours somatic cell cellular changes gamete cell days acute direct damage next generation weeks/ month neoplasms (cancer, leukemia) years non-malignant later damage deterministic stochastic genetic damage 11
12 Direct vs. Indirect Radiation Effect indirect direct 12
13 DNA damages Single-/ Double-strand breaks Chemical bond between Neighboring nucleotides Chemical modification of a nucleotide (mutation) / losing of one nucleobase Chemical linkage of two strands 13
14 DNA damages spontaneous radiation-induced Event per second per hour per year per mgy Single-strand break 1.4 ca. 5 x 10 3 ca. 4.4 x Double-strand break 0.04 Depurination ca. 1.5 x 10 3 ca. 1.4 x Base damage 0.8 ca x 10 3 ca. 1.1 x Total 2.2 ca. 8 x 10 3 ca.7 x 10 7 ca
15 Radiation damages 15
16 Stochastic vs. deterministic effects Bei den somatischen Strahlenwirkungen unterscheidet man zwischen stochastischen und deterministischen Strahlenwirkungen. 16
17 Deterministic radiation damages 17
18 Deterministic radiation damages Deterministic Radiation Damage 18
19 Deterministic radiation damages Strahlenverbrennung der Haut Strahlendermatitis und Epilation 19
20 Dose limits Equivalent Dose Limits StSG ( ) / StSV ( ) Equivalent Dose Limits (annual) Body Equivalent Dose Limits for tissues & organs (annual) Lens of eye Skin, hands, and feet 1 msv (public) 20 msv (people working with activity) max. 50 msv (exceptional with permission) 150 msv 500 msv 20
21 Shielding Lab coat: Shields already approx. 80% of soft β-radiation Neutrons: Moderation with materials that contain a lot of protons (e.g. water) Absorption with B, Gd or Cd (leads to secondary γ-radiation) 21
22 Square Root Law of Distance r1 H 2 = H 1 r
23 ALARA As Low As Reasonable Achievable Duration of stay (Aufenthaltszeit) Distance (Abstand) Shielding (Abschirmung) Activity Avoid contamination / incorporation 23
24 Dose estimation 24
25 Dose estimation Organ Dose Skin Dose Contamination H p 2 1m = A t h10 r HS = A t h 0.07 H A = t h F S c0.07 h 10 : Dose in msv per GBq and per hour in 1 m distance to the source h 0.07 : Dose in msv per GBq and per hour in 10 cm distance to the source Rule-of-thumb 1 GBq in 1 m distance during 1 h leads to a H p of 1/3 msv 25
26 Dose estimation 26
27 Dose estimation 27
28 Dose estimation A technician should work 3 h with 75 MBq I-125. The distance between the source and the body will be in average 0.5 m. What dose (Tiefenäquivalentdosis) will he accumulate? h 10 I-125 = 0.033(mSv/h)/GBq in 1 m distance A technician works 20 min without any shielding with 200 MBq of C-14. What skin dose did he accumulated? h 0.07 C-14 = 200 (msv/h)/gbq in 10 cm distance After 2h, a skin contamination of 10 cm 2 with 1000 Bq Cs-137 has been detected and cleaned. What skin dose has been accumulated? h c0.07 C-14 = 1.5 (msv/h)/(kbq/cm 2 ) 28
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Name Date Class. alpha particle radioactivity gamma ray radioisotope beta particles radiation X-ray radioactive decay
Name Date _ Class _ Nuclear Chemistry Section.1 Nuclear Radiation In your textbook, read about the terms used to describe nuclear changes. Use each of the terms below just once to complete the passage.