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IAEA Artificial Sources of Radiation Sealed and unsealed – Isotope Production Day 4 – Lecture 1 1.

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Presentation on theme: "IAEA Artificial Sources of Radiation Sealed and unsealed – Isotope Production Day 4 – Lecture 1 1."— Presentation transcript:

1 IAEA Artificial Sources of Radiation Sealed and unsealed – Isotope Production Day 4 – Lecture 1 1

2 IAEA To discuss about artificial sources of radiation, characteristics of a sealed and an unsealed source and the how the isotopes are produced Objectives 2

3 IAEA Radionuclide Sources Sample Alpha, Beta, Gamma, X-ray and Neutron Sources Sealed and an Unsealed Sources Production of Radioactive Isotopes Isotope Generators Contents 3

4 IAEA ExampleSpecial UnitsSI Units (37x) environmental samplespicocurie10 -12 millibequerel10 -3 laboratory standardnanocurie10 -9 becquerel10 0 in-vitro tracermicrocurie10 -6 kilobequerel10 3 nuclear medicinemillicurie10 -3 megabequerel10 6 calibration sourcecurie10 0 gigabequerel10 9 teletherapy sourcekilocurie10 3 terabequerel10 12 irradiatormegacurie10 6 petabequerel10 15 Relative Radioactive Source Activity 4

5 IAEA Reactor Fuel Fission Products Activation Products Non-Reactor Medical Industrial Military Aviation Support Research Commercial Where Radionuclides are Found 5

6 IAEA Samples of Radionuclide Sources  Medical  Human Use (MBq-TBq)  Nuclear Medicine  Diagnostic ( 99m Tc, 131 I, 153 Gd, 125 I, 201 Tl)  Therapeutic ( 131 I, 32 P, 89 Sr)  Radiation Therapy  Teletherapy ( 60 Co)  Brachytherapy ( 137 Cs, 192 Ir, 198 Au, 125 I, 109 Pd)  Non-Human Use (KBq)  In-Vitro Laboratory ( 125 I, 51 Cr, 59 Co) 6

7 IAEA  Industrial (GBq-PBq)  Radiography ( 192 Ir, 60 Co, 137 Cs)  Well Logging ( 241 Am, 137 Cs, 60 Co, 238 U, 131 I, 3 H)  Irradiators ( 60 Co, 137 Cs)  Gauges  Fixed ( 137 Cs, 60 Co, 147 Pm)  Portable ( 241 Am, 137 Cs)  Fuel Cycle (U) Samples of Radionuclide Sources 7

8 IAEA  Support (KBq or less)  Calibration/Check Sources ( 60 Co, 137 Cs, 239 Pu, 241 Am, 252 Cf, 238 U, 90 Sr, 232 Th)  Laboratory Standards (many)  Research (MBq)  Chromatographs ( 63 Ni)  Education (many) Samples of Radionuclide Sources 8

9 IAEA  Commercial (varies – typically MBq or less)  Personal  Wristwatches ( 3 H, 147 Pm)  Dinnerware (U)  Recreational  Lantern Mantles ( 232 Th)  Safety  Smoke Detectors ( 241 Am)  Warning/Exit Signs ( 3 H)  Shielding ( 238 U)  Service  Anti-Static Devices ( 210 Po) Samples of Radionuclide Sources 9

10 IAEA  Military (MBq)  Non-Nuclear Weapons  Armor Piercing Projectiles ( 238 U)  Survival  Lensatic Compasses ( 3 H, 147 Pm)  Chemical Agent Monitors ( 63 Ni, 241 Am, 3 H) Samples of Radionuclide Sources 10

11 IAEA  Aviation (Bq-MBq)  Operational  Fixed Wing Aircraft  Oil Level Indicators ( 85 Kr)  Aileron Counterweights ( 238 U)  Magnesium/Nickel Skin Panels ( 232 Th)  Spark Gaps/Igniters ( 60 Co)  Helicopter  Blade Integrity and Ice Detection ( 90 Sr) Samples of Radionuclide Sources 11

12 IAEA  Aviation (MBq-TBq)  Historic Displays/Vintage Aircraft ( 226 Ra)  Safety Items  Runway Lights, Markers and Exit Signs ( 3 H) Samples of Radionuclide Sources 12

13 IAEA Sample Alpha, Beta, Gamma Sources 13

14 IAEA Sample Alpha Sources 14

15 IAEA Sample Beta Sources 15

16 IAEA Sample Gamma Sources 16

17 IAEA Sample Neutron Sources Most neutron sources are either alpha-beryllium sources (Pu-Be, Am-Be, Ra-Be, Po-Be etc) or Californium-252 17

18 IAEA Sample X-Ray Sources 18

19 IAEA Sealed Source 19

20 IAEA Sealed Source 20

21 IAEA Sealed Source 18 mm 19 mm 21

22 IAEA Sealed Source 19 mm 22

23 IAEA Sealed Source 23

24 IAEA Sealed Source 24

25 IAEA Unsealed Source 25

26 IAEA Production of Isotopes  Most commercially available isotopes used in Medicine and Industry are produced by neutron bombardment in reactors (Byproduct Material) or by charged particle bombardment in accelerators (NARM).  Some isotopes are obtained from the decay of other isotopes which were produced by the processes listed above. An examples of this type of isotope is 99m Tc which is obtained form the decay of 99 Mo which is itself derived from fission (Byproduct Material). 26

27 IAEA Production of Radionuclides TargetReactionRadionuclide Cr-50(n,γ) Cr-51 Mo-98 (n, γ) Mo-99 Xe-124 (n, γ) Xe-125 => I-125 Te-130 (n, γ) Te-131 => I-131 Zn-68(p,2n) Ga-67 Cd-111 (p,n) In-111 Tl-203 (p,3n) Pb-201 => Tl-201 Te-124 (p,2n) I-123 I-127(p,5n) Xe-123 => I-123 U-235 (n,f) Zr-99 => Nb-99 => Mo-9 27

28 IAEA CYCLOTRON Uppsala, Sweden 28

29 IAEA Isotope Generators 29

30 IAEA ParentDaughter 52 Fe 52m Mn 62 Zn 62 Cu 68 Ge 68 Ga 72 Se 72 As 82 Sr 82 Rb 118 Te 118 Sb 122 Xe 122 I Isotope Generators ParentDaughter 128 Ba 128 Cs 191 Os 191m Ir 195m Hg 195m Au 81 Rb 81m Kr 178 W 178 Ta 188 W 188 Re 115 Cd 115m In 30

31 IAEA ParentHalf LifeDaughterHalf Life 66 Ni2.3d 66 Cu5.1m 69m Zn0.6d 69 Zn55m 112 Pd0.9d 112 Ag3.2h 115 Cd2.2d 115m In4.5h 128 Ba2.4d 128 Cs3.6m 132 Te3.2d 132 I2.3h 188 W69.4d 188 Re17h 224 Ra/ 212 Pb3.7d 212 Bi1h 225 Ra14.8d 213 Bi46m Isotope Generators 31

32 IAEA Where to Get More Information  Cember, H., Johnson, T. E, Introduction to Health Physics, 4th Edition, McGraw-Hill, New York (2009)  International Atomic Energy Agency, Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources (PGEC), Training Course Series 18, IAEA, Vienna (2002) 32


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