Radioactivity & Radionuclide Production

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RADIOACTIVITY & RADIONUCLIDE PRODUCTION

Dr. Mohammed Alnafea [email protected] www.dralnafea.com

History of Radiopharmacy

Medicinal applications since the

discovery of Radioactivity Early 1900’s Limited understanding of Radioactivity and dose 2

1912 — George de Hevesy Father of the “radiotracer” experiment. Used a lead (Pb) radioisotope to prove the recycling of meat by his landlady. Received the Nobel Prize in chemistry in 1943 for his concept of “radiotracers”

3

Early use of radiotracers in medicine 1926: Hermann Blumgart, MD injected 1-6 mCi of “Radium

C” to monitor blood flow (1st clinical use of a radiotracer)

1937: John Lawrence, MD used phosphorus-32 (P-32) to

treat leukemia (1st use of artificial radioactivity to treat patients)

1937: Technetium discovered by E. Segre and C. Perrier

4

Early Uses continued  1939: Joe Hamilton, MD used radioiodine (I-131) for

diagnosis

 1939: Charles Pecher, MD used strontium-89 (Sr-89) for

treatment of bone metastases.

 1946: Samuel Seidlin, MD used I-131 to completely cure

all metastases associated with thyroid cancer. This was the first and remains the only true “magic bullet”.

 1960: Powell Richards developed the Mo-99/Tc-99m

generator

 1963: Paul Harper, MD injected Tc-99m pertechnetate for

human brain tumor imaging

5

Part 1: Characteristics of a Radiopharmaceutical What is a radiopharmaceutical? A radioactive compound used for the diagnosis and

therapeutic treatment of human diseases.

Radionuclide + Pharmaceutical 6

Radioactive Materials Chart of the Nuclides ↑ Z

N→

Unstable nuclides Combination of neutron and protons Emits particles and energy to

become a more stable isotope 7

Radiation decay emissions

Alpha (α or

He2+ ) Beta (β − or e-) Positron (β +) Gamma (γ ) Neutrons (n) 4

8

Radioactivity  In 1896 Henri Becquerel -> find that the photographic plate had been

darkened in the part nearest to uranium compounds. He called this phenomenon radioactivity.

 Radioactivity (radioactive decay) is the spontaneous break up

(decay) of atoms.

 Marie Curie (student of Becquerel) examined the radioactivity of

uranium  compound and she discovered that:

 1. All uranium compounds are radioactive  2. Impure uranium sulphide contains two other elements which are

more radioactive  than uranium.  3. Marie named these elements radium & polonium.  4. Radium is about two million times more radioactive than uranium.

9

Alpha, Beta & gamma radiation When the radioactive atoms break up,

they release energy and lose three kinds of radiation (Alpha, Beta & gamma radiation).  Alpha & Beta are particles where as gamma-

rays are electromagnetic wave with the greatest penetrating power.  These radiation

10

Interactions of Emissions  Alpha (α or 4He)

 High energy over short

linear range  Charged 2+  Beta (β

-

or e-)

 Various energy, random

motion  negative

 Gamma (γ )

 No mass, hv

11

 Positron (β +)  Energy >1022 MeV, random

motion  Anihilation (2 511 KeV ~180°)  Neutrons (n)  No charge, light elements

Physical Half Life and Activity Radioactive decay is a

statistical phenomenon t1/2 λ = decay constant decay constant is the Number of atoms decaying per unit time is proportional to the number of  Activity is the amount of unstable radioactive material atoms

Half-life is time needed to decrease nuclides by 50%

12

Measured Activity  In practicality, activity (A)

is used instead of the number of atoms (N).  A= cλ t, m where c is the detection coefficient A=AOe-λ t  Units Curie (Ci), 3.7E10 decay/s 1 g Ra Becquerel (Bq) 1 decay/s

Half Life and decay constant  Half-life is time needed to decrease nuclides by 50%  Relationship between t1/2 and λ N/No=1/2=e-λ

t

ln(1/2)=-λ t1/2 ln 2= λ t1/2 t1/2 =(ln 2)/λ

14

NB: Physical half-life and decay constant are inversely related and unique for each radionuclide

Why use radioactive materials ? Radiotracers High sensitivity  Radioactive emission (no interferences) Nuclear decay process  Independent reaction  No external effect (chemical or biochemical)

Active Agent  Monitor ongoing processes

15

Applications in Nuclear Medicine Imaging Gamma or positron emitting isotopes  99m Tc, 111 In, 18 F, 11 C, 64 Cu Visualization of a biological process  Cancer, myocardial perfusion agents

Therapy Particle emitters Alpha, beta, conversion/auger electrons  188 Re, 166 Ho, 89 Sr, 90 Y, 212 Bi, 225 Ac, 131 I Treatment of disease  Cancer, restenosis, hyperthyroidism

16

Ideal Characteristics of a Radiopharmaceutical Nuclear Properties Wide Availability Effective Half life (Radio and biological) High target to non target ratio Simple preparation Biological stability Cost

17

Ideal Nuclear Properties for Imagining Agents Reasonable energy emissions. Radiation must be able to penetrate several

layers of tissue. No particle emission (Gamma only) Isomeric transition, positron (β +), electron

capture High abundance or “Yield” Effective half life Cost

18

Detection Energy Requirements  Best images between 100-

300 KeV  Limitations  Detectors (NaI)  Personnel (shielding)  Patient dose

 What else happens at

higher energies? Lower photoelectric peak abundance, due to the Compton effect

Cs-137 decay (662 KeV)

Energy → 19

Gamma Isotopes Radionuclide T1/2 Tc-99m Tl-201 In-111 Ga-67 I-123 13.2 I-131 8d Xe-133

20

γ (%)

6.02 hr 140 KeV (89) 73 hr 167 KeV (9.4) 2.21 d 171(90), 245(94) 78 hr 93 (40), 184 (20), 300(17) hr 159(83) 284(6), 364(81), 637(7) 5.3 d 81(37)

Radioactive Decay Kinetics

21

Basic decay equations  The radioactive process is a subatomic change

within the atom  The probability of disintegration of a particular atom of a radioactive element in a specific time interval is independent of its past history and present circumstances  The probability of disintegration depends only on the length of the time interval.

Probability of decay: p=λ ∆ t Probability of not decaying: 1-p=1- λ ∆ t 22

Summary: The Radioactive Decay Law • The radioactive decay law in equation form;

• Radioactivity is the number of radioactive decays per unit time; • The decay constant is defined as the fraction of the initial number of radioactive nuclei which decay in unit time; • Half Life: The time taken for the number of radioactive nuclei in the sample to reduce by a factor of two; • Half Life = (0.693)/(Decay Constant); • The SI Unit of radioactivity is the becquerel (Bq) 1 Bq = one radioactive decay per second;

23

• The traditional unit of radioactivity is the curie (Ci); 1 Ci = 3.7 x 1010 radioactive decays per second

ATOMIC STRUCTURE Atomic number (Z):

number of protons in nucleus Mass number (A):

Number of protons + neutrons Neutron number (N):

Nuclear forces:

• "Strong" attractive force • electrostatic repulsive force   Radioactive decay caused by nuclear instability Due to p-p electrostatic repulsion 24

RADIONUCLIDE DECAY MODES

Number of neutrons (A-Z)

Stable nuclei Unstable – radioactive : halflife < 1ms Unstable – radioactive : halflife > 1000 years

No stable nuclei when Z > 83 or N > 126

Number of protons (Z)

25

Nuclear Transformation When the atomic nucleus undergoes

spontaneous transformation, called radioactive decay, radiation is emitted If the daughter nucleus is stable, this

spontaneous transformation ends If the daughter is unstable, the process continues until a stable nuclide is reached Most radionuclides decay in one or more

of the following ways: (a) alpha decay, (b) beta-minus emission, (c) beta-plus (positron) emission, (d) electron capture, or (e) isomeric transition.

26

RADIONUCLIDE DECAY MODES

27

No stable nuclei when Z > 83 or N > 126

Alpha Decay Alpha (α ) decay is the spontaneous

emission of an alpha particle (identical to a helium nucleus) from the nucleus.

Typically occurs with heavy

A Z 28

nuclides (A > 150) and is often followed by gamma and characteristic x-ray emission A−4 4 +2

X → Z− 2Y + 2 He + transition energy

RADIONUCLIDE DECAY MODES α decay

Nuclei with  Z > 83 29

Beta-Minus (Negatron) Decay Beta-minus (β -) decay characteristically

occurs with radionuclides that have an excess number of neutrons compared with the number of protons (i.e., high N/Z ratio) A A Z

X→ Z+1Y + β + ν + energy

Any excess energy in the nucleus after

beta decay is emitted as gamma rays, internal conversion electrons or other associated radiations

30

31

RADIONUCLIDE DECAY MODES β - decay

 Occurs in nuclei with

high neutron:proton ratio

32

Beta-Plus Decay (Positron Emission) Beta-plus (β +) decay characteristically

occurs with radionuclides that are “neutron poor” (i.e., low N/Z ratio) A Z

X→ Y + β + ν + energy A Z-1

+

Eventual fate of positron is to annihilate

with its antiparticle (an electron), yielding two 511-keV photons emitted in opposite directions 33

34

RADIONUCLIDE DECAY MODES β + decay

 Occurs in nuclei with a

low neutron:proton ratio

35

Electron Capture Decay Alternative to positron decay for neutron-

deficient radionuclides.

Nucleus captures an orbital (usually K- or

L-shell) electron A Z

X + e- →

Y + ν + energy

A Z -1

Electron capture radionuclides used in

medical imaging decay to atoms in excited states that subsequently emit detectable gamma rays

36

RADIONUCLIDE DECAY MODES Electron capture

 Occurs in nuclei with a

low neutron:proton ratio

37

RADIONUCLIDE DECAY MODES γ emission

 Generally accompanies other radioactive decay  associated with energy loss from changes in nuclear

energy states

38

RADIONUCLIDE DECAY MODES Spontaneous fission

 Used by high Z nuclei  2 nuclei of approximately

equal mass produced

 Accompanied by release

of energy and neutrons

39

Summary: Radioactive Decay Fission: Some heavy nuclei decay by splitting into 2

or 3 fragments plus some neutrons. These fragments form new nuclei which are usually radioactive; Alpha Decay: Two protons and two neutrons leave the nucleus together in an assembly known as an alpha-particle; An alpha-particle is a He-4 nucleus; Beta Decay - Electron Emission: Certain nuclei with an excess of neutrons may reach stability by converting a neutron into a proton with the emission of a beta-minus particle; A beta-minus particle is an electron; 40

Summary: Radioactive Decay Beta Decay - Positron Emission: When the number of

protons in a nucleus is in excess, the nucleus may reach stability by converting a proton into a neutron with the emission of a beta-plus particle; A beta-plus particle is a positron; Positrons annihilate with electrons to produce two back-to-back gamma-rays; Beta Decay - Electron Capture: An inner orbital electron is attracted into the nucleus where it combines with a proton to form a neutron;

41

Summary: Radioactive Decay Electron capture is also known as K-capture; Following electron capture, the excited nucleus may give off

some gamma-rays. In addition, as the vacant electron site is filled, an X-ray is emitted; Gamma Decay - Isomeric Transition: A nucleus in an excited state may reach its ground state by the emission of a gammaray; A gamma-ray is an electromagnetic photon of high energy; Gamma Decay - Internal Conversion: the excitation energy of an excited nucleus is given to an atomic electron.

42

Q1:Half-life calculation Using Nt=Noe-λ t For an isotope the initial count rate was 890 Bq. After 180 minutes the count rate was found to be 750 Bq.What is the half-life of the isotope?

43

Q2: Half-life calculation A=λ N  A 0.150 g sample of 248Cm has a alpha activity of 0.636 mCi.What is the half-life of 248Cm?

44

Isomeric Transition During radioactive decay, a daughter

may be formed in an excited state.

Gamma rays are emitted as the

daughter nucleus transitions from the excited state to a lower-energy state. Some excited states may have a halflives ranging up to more than 600 years Am Z 45

X → X + energy A Z

Decay Schemes Each radionuclide’s decay process is a

unique characteristic of that radionuclide.

Majority of pertinent information about the

decay process and its associated radiation can be summarized in a line diagram called a decay scheme.

Decay schemes identify the parent,

daughter, mode of decay, intermediate excited states, energy levels, radiation emissions, and sometimes physical half-life.

46

Generalized Decay Scheme

47

48

49

50

51

52

Radionuclide Production All radionuclides commonly administered to

patients in nuclear medicine are artificially produced. Most are produced by cyclotrons, nuclear

reactors, or radionuclide generators

53

Cyclotrons Cyclotrons produce radionuclides by

bombarding stable nuclei with high-energy charged particles.

Most cyclotron-produced radionuclides are

neutron poor and therefore decay by positron emission or electron capture.

Specialized hospital-based cyclotrons have been

developed to produce positron-emitting radionuclides for positron emission tomography (PET) Usually located near the PET imager because of short

half-lives of the radionuclides produced

54

55

56

57

Nuclear Reactors Specialized nuclear reactors used to produce

clinically useful radionuclides from fission products or neutron activation of stable target material.

Uranium-235 fission products can be chemically

separated from other fission products with essentially no stable isotopes (carrier) of the radionuclide present.

Concentration of these “carrier-free” fission-

produced radionuclides is very high

58

59

NUCLEAR REACTOR Schematic Representation

60

RADIONUCLIDE PRODUCTION Thermal neutron induced fission

U is most commonly used fissionable material



235



235

E

U + n → unstable nucleus → fission fragments + n +



average number of neutrons per fission = 2.4



self-irradiation of 235U - self sustaining chain reaction



moderators included to slow neutrons to thermal energies - deuterium oxide, graphite

61

RADIONUCLIDE PRODUCTION Thermal neutron induced fission



U fission → > 370 nuclides

235

• observed mass range : 72 - 161 • distribution as indicated

62

RADIONUCLIDE PRODUCTION Thermal neutron induced fission



radionuclides extracted when fuel elements replaced



chemical separation techniques used • precipitation, solvent extraction, chromatography



products usually carrier free, high specific activity



fission produced radionuclides usually neutron rich • decay by β - emission

• 63

relatively cheap - not major function of reactor

RADIONUCLIDE PRODUCTION Reactor Targetry



irradiation positions

• mobile : short irradiation times (minutes - 1 week) • fixed : long irradiation times (one or more reactor fuel cycles : 2 - 4 weeks) • • •



accessible only during reactor shutdown both positions water cooled reactor temperature ≈ 100°C, sample temperature > 1000°C (γ heating)

target design

• pure element often best choice – high melting point and density • prevention of target rupture primary safety consideration • use of mercury and cadmium prohibited • reactivity of mercury with aluminium (fuel cans) • high neutron absorption of cadmium (reactor operation)

64

RADIONUCLIDE PRODUCTION Neutron bombardment



Activity of a radionuclide produced by particle bombardment is given by A = φ Nσ (1 - e-λ t)

where: A = activity φ = particle flux (number/cm2/s) N = number of target atoms σ = absorption cross section in barns (10-24 cm2/atom) λ = decay constant of product radionuclide t = duration of irradiation (in seconds)

• • • 65

when t > 4 x T½ , (1 - e-λ t) approaches 1 saturation activity : A = φ Nσ no gain from irradiating beyond 3 - 4 x T½

RADIONUCLIDE PRODUCTION Preparation of I-131 (carrier)



Starting material : 2.5g 93+% 235U



flux: 2 x 1014n/cm2/sec, 28d



target stored for 7d following irradiation



dissolved in 4.5M NaOH + heating 133

Xe released - trapped (charcoal, liquid N2)

Al2O3.2H2O + NaI + H2SO4 + H2O2 - distilled

≈ 7500 GBq 131 I (+ 127 I + 124 I) i.e. carrier iodine 235

66

U recovered for reuse

RADIONUCLIDE PRODUCTION Preparation of I-131 (carrier free)



target : 2.5g 99+% 130Te



Neutron flux: 2 x 1014n/cm2/sec, 21d



130



≈ 65 GBq 131I obtained by distillation, as before



130

67

Te (n,γ ) 131Te 

I

131

Te recovered for reuse

RADIONUCLIDE PRODUCTION

Preparation of Mo-99 (non-fission + fission) •

target : natural MoO3 - 23.78%



flux: 2 x 1014 n/cm2/sec, 7d



98



≈ 37 GBq 99 Mo from 1g MoO3



natural MoO3  98 Mo used



Starting material : 2.5g 93+% 235 U



99



produced in 1000 GBq quantities



high specific activity for generators

68 •

98

Mo

Mo (n,γ ) 99 Mo 185

W (T½ = 74d) - absent when enriched

Mo extracted from acidified solution of fission products

may contain some 131 I and 103 Ru

REACTOR PRODUCED RADIONUCLIDES PRODUCT

DECAY MODE PRODUCTION REACTION

14

C

β-

14

N(n,p)14 C

32

P

β-

31

51

Cr

EC, γ

50

Cr(n,γ)51 Cr

59

Fe

β-, γ

58

Fe(n,γ)59 Fe

125

I

EC, γ

124

Xe(n,γ)125 Xe

131

I

β-, γ

130

Te(n,γ)131 Te

P(n,γ)32 P

I

EC 125 β- 131

69

I

RADIONUCLIDE PRODUCTION Radionuclide Generators



allows distribution of short lived nuclides to centres remote from production site



long(er) lived parent nuclide decays to daughter nuclide



allows separation of daughter from parent



separation achieved by difference in chemical properties e.g. charge - ion exchange chromatography

70

RADIONUCLIDE GENERATORS

Cross-section of a typical radionuclide generator

71

RADIONUCLIDE GENERATORS Radioactive Decay Laws



common simplifications



T½ parent ≈ 10 x T½ daughter



transient equilibrium



λd Ad ( t ) = Ap λ p − λd

e.g. 99Mo / 99Tcm generator 66h

72

6.02h

RADIONUCLIDE GENERATORS Radioactive Decay Laws



common simplifications



T½ parent >> T½ daughter (λ p >> λ d)





73

secular equilibrium

Ad ( t ) = Ap (1 − e

− λdt

e.g. 68 Ge / 68 Ga generator 270d 68m

)

RADIONUCLIDE GENERATORS Desirable Properties

74



ease of operation



daughter should have high chemical and radionuclidic purity



daughter should be a different chemical element to parent



should remain sterile and pyrogen free



daughter should be in a form suitable for preparation of radiopharmaceuticals

Technetium Generator Elution

75

RADIONUCLIDE GENERATORS Yield Problems



yield is always < 100%



caused by reduced access of eluant to support bed due to • poor quality ion exchange

material

• channelling in column during

transportation

• improper initial packing of

column

• terminal sterilisation

procedures

• pseudochannelling - dry vs.

wet generators

76

Commonly Used Radionuclides Nuclide IMAGING 18 F 67 Ga 81 Krm 99 Tcm 111 In 123 I 131 I 201 Tl THERAPY 90 Y 186 Re In Vitro 14 C 51 Cr 77 125 I

Characteristics

Production Method

Decay Mode

γ Emissions Half-life (keV)

Cyclotron Cyclotron Generator Generator Cyclotron Cyclotron Reactor Cyclotron

Positron EC IT IT EC EC Beta EC

511 92, 182, 300, 390

68-80

108 min 78 hr 13 s 6 hr 67 hr 13 hr 8d 73.5 hr

Reactor Reactor

Beta Beta

137

64 hr 90 hr

Reactor Reactor Reactor

Beta EC EC

323 27-35

5760 yr 27.8 d 60d

191 140 173, 247 160 280, 360, 640

Assignment The way of FDG interaction in the body. literature review about hypoxia & tumour

hypoxia. PET and radiopharmaceutical

78

Neutron Activation Neutrons produced by the fission of uranium in a

nuclear reactor can be used to create radionuclides by bombarding stable target material placed in the reactor. Process involves capture of neutrons by stable

nuclei. Almost all radionuclides produced by neutron

activation decay by beta-minus particle emission

79

80

Radionuclide Generators Technetium-99m has been the most important

radionuclide used in nuclear medicine Short half-life (6 hours) makes it impractical to store even a weekly supply Supply problem overcome by obtaining parent Mo99, which has a longer half-life (67 hours) and continually produces Tc-99m A system for holding the parent in such a way that the daughter can be easily separated for clinical use is called a radionuclide generator

81

82

83

Transient Equilibrium Between elutions, the daughter (Tc-

99m) builds up as the parent (Mo-99) continues to decay.

After approximately 23 hours the Tc-

99m activity reaches a maximum, at which time the production rate and the decay rate are equal and the parent and daughter are said to be in transient equilibrium.

84

Transient Equilibrium Once transient equilibrium has been

reached, the daughter activity decreases, with an apparent half-life equal to the half-life of the parent.

Transient equilibrium occurs when the

half-life of the parent is greater than that of the daughter by a factor of ~10

85

86

87

Secular Equilibrium If the half-life of the parent is very much longer

than that of the daughter (I.e., more than about 100× longer), secular equilibrium occurs after approximately five to six half-lives of the daughter.

In secular equilibrium, the activity of the parent and

the daughter are the same if all of the parent atoms decay directly to the daughter.

Once secular equilibrium is reached, the daughter

will have an apparent half-life equal to that of the parent

88

89

Ideal Radiopharmaceuticals Low radiation dose High target/nontarget activity Safety Convenience Cost-effectiveness

90

Mechanisms of Localization Compartmental localization and leakage Cell sequestration Phagocytosis Passive diffusion Metabolism Active transport

91

Localization (cont.) Capillary blockade Perfusion Chemotaxis Antibody-antigen complexation Receptor binding Physiochemical adsorption

92

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