Transcript lecture 4.ppt

Nuclear pharmacy
Lecture 4
Production of radionuclides
Introduction
● In 1896 Becquerel discovered the natural radioactive in
potassium uranyl sulfate.
● Since then, Pierre and Marie Curie, Rutherford, and Soddy have
all made tremendous progress in the discovery of many other
radioactive elements.
● The work of all these scientists has shown that all elements
found in nature with an atomic number greater than 83
(bismuth) are radioactive.
● Artificial radioactivity was first reported by I. Curie and F.
Joliot in 1934. These scientists irradiated boron and aluminum
targets with α particles from polonium and observed positrons
emitted from the target even after the removal of the α particle
source. This discovery of induced or artificial radioactivity
opened up a brand new field of tremendous importance.
● Around the same time, the discovery of the cyclotron neutron
and deuteron by various scientists added to the production of
many more artificial radioactivities.
● At present, more than 1500 radionuclides have been produced
artificially in the cyclotron, the reactor, the neutron generator,
and the linear accelerator.
● Radionuclides used in nuclear medicine are mostly artificial
ones. They are primarily produced in a cyclotron or a reactor.
The type of radionuclide produced in a cyclotron or a reactor
depends on the irradiating particles, its energy and the target
nuclei.
Radionuclides production
 All radionuclides commonly administered to patients in nuclear
medicine are artificially produced.
 Most are produced by cyclotrons, nuclear reactors, or
radionuclide generators
Types of radioactivity: How to produce a radioactive
nuclide ?
1. Natural radioactivity:
Nuclear reactions occur spontaneously.
2. Artificial radioactivity:
The property of radioactivity produced by particle bombardment or
electromagnetic irradiation.
A- Charged-particle reactions
Reactions of these types may be produced with
e.g. protons (1 1H or P)
e.g. deuterons (2 1H or d)
e.g. alpha particles (4He or α)
B- Photon-induced reactions
Electromagnetic radiations or photons may induce nuclear
reactions. The source of electromagnetic energy may be
gamma-emitting radionuclide or high-voltage x-ray generator.
C- Neutron-induced reactions
It is the most widely used method It is the bombardment of a non radioactive target nucleus with
a source of thermal neutrons.
-
Production of radionuclides:
1. Charged particle bombardment
Radionuclides may be produced by bombarding target materials with charged
particles in particle accelarators such as cyclotrons.
A cyclotron consists of : Two flat hollow objects called dees.
The dees are part of an electrical circuit.
On the other side of the dees are large magnets that (drive) steer the injected
charged particles (protons, deutrons, alpha and helium) in a circular path
The charged particle follows a circular path until the particle has sufficient
energy that it passes out of the field and interact with the target nucleus.
Cyclotron
Cyclotron-produced isotopes (accelerator):
- It can be used only with charged particles such as: electrons,
protons, deuterons because the operation of such machine depends
upon the interaction of magnetic and/or electrostatic fields with the
charge of the particle undergoing acceleration.
- When the particles have been accelerated to a high velocity, they are
caused to strike a target, containing the atoms to be bombarded.
- Sodium 22 is prepared in this way by the interaction of high velocity
deuterons with magnesium 24.
24Mg (d, α) 22Na where 24Mg is the target, the deuteron (d) is the irradiating
particle, the α is the emitted particle, and 22Na is the product radionuclide.
Other medically important ultra-short-lived radionuclides which have been produced in a cyclotron by use of high-energy deuterons include
11C, 13N, 15O.
Example:
Carbon-11 has a half-life of 20.4 min and can be produced by
10B (d, n) 11C
Short-Lived Radionuclides
most of which are used to positron emission tomography (PET)
Carbon-11 ( t1/2 = 20.4 min )
Nitrogen-13 ( t1/2 = 10 min )
Oxygen-15 ( t1/2 = 2 min )
Fluorine-18 (t1/2 = 110 min)
- Those which have been produced using high-energy alpha particles
include 18F, 123I, 124I.
- High energy protons have been used to produce 127Xe, 201Pb, 111In,
67Ga.
For example: 68Zn (p,2n) 67Ga, 111Cd (p, n)111In
- Most cyclotron-produced radionuclides are neutron poor
and therefore, decay by positron emission or electron
capture. These positron emitters are very useful in
imagining by positron emission tomography (PET).
- Since various isotopes of different elements may be
produced in a particular irradiating system, it is necessary
to isolate isotopes of a single element, this can be
accomplished by appropriate chemical methods such as
solvent extraction, precipitation, and distillation.
- Iodine-123 has gained considerable importance in nuclear
medicine because it has good radiation characteristics. It is
produced directly or indirectly in a cyclotron by several nuclear
reactions.
● Direct nuclear reactions, whereby 123I is produced directly and
likely to be contaminated with other iodine radioisotopes such as
124I and 125I, depending on the type of target and irradiating
particle. 121Sb (α, 2n)123I
123Te (p, n)123I
● In direct nuclear reaction is so chosen that 123Xe is produced
initially, which then decays with a half-life of 2.1hr to produce 123I
with a half-life of 13hr. These reactions allow the production of
123I free of other radioisotopes of iodine.
123Te (α, 2n) 123Xe
127I (p, 5n) 123Xe
2- Neutron bombardment
● Radionuclides may be produced by bombarding target materials with
neutrons in nuclear reactors.
● The majority of radiopharmaceuticals are produced by this process.
● The nuclear reactors are devices for producing high fluxes of neutrons.
● Specialized nuclear reactors used to produce clinically useful
radionuclides from fission products or neutron activation of stable
target material
● A nuclear reactor is constructed with fuel rods made of fissile materials
such as enriched 238U and 239Pu. These fuel nuclei undergo spontaneous
fission with extremely low probability.
● Fission is defined as the break up of a heavy nucleus into two fragments of
approximately equal mass, accompanied by the emission of 2-3 neutrons with mean
energies of about 1.5 MeV (low probability of interaction with other nuclei). Neutrons
with thermal energy (0.025 eV) interact with many other nuclei, efficiently producing
various radionuclides.
 Neutrons are usually created by nuclear fission where the nuclei
are split which; a process that releases energy.
 The nuclear reactors work by fission. The element uranium is the
main fuel and is easily split by thermal neutrons diffusing into the
nucleus. In the process several new high energy neutrons are
created, moderated in energy and are used to do new reactions –
chain reaction.
 This chain reaction , ultimately leading to an explosive situation in
the reactor.
● This chain reaction must be controlled, excess neutrons (more
than one) are removed by positioning cadmium (cd) rods in the
fuel core (cadmium has a high probability of absorbing a
thermal neutron).
●In order to make the high-energy or so-called fast neutrons more
useful, they are thermalized or slowed down by interaction
with low molecular weight materials, such as heavy water,
beryllium and graphite, which are distributed in the spaces
between the fuel rods (moderators).
Schematic Diagram of a Nuclear Reactor
Nuclear Reactors
The reaction is kept in
check by the use of
control rods.

These block the paths of
some neutrons, keeping
the system from reaching
a dangerous supercritical
mass.

 The neutrons in reactor are mixture of fast neutrons (high energy)
and thermal neutrons have higher probability of causing nuclear
reaction.
 In the reactor the uranium fission reaction produces a large supply of
neutrons.
- One neutron for each uranium atom undergoing fission is used to
sustain the reaction.
- The remaining neutrons are used either to produce plutonium by
interaction with 238U nuclei or are used to produce radioactive
products by causing the neutrons to interact with specific substances
which have been inserted into the pile (neutron activation)
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.
 In the reactor, two types of interaction with thermal neutrons are of
considerable importance in the production of various useful
radionuclides:
● Fission of heavy elements
1. fissionable heavy elements : some nuclides having atomic number greater than 92. (235U,
239Pu, 237Np, 233U, 233Th ).
2. The atomic number of nuclide produced by fission is about 28 to 65.
3. The methods used to product separation are : precipitation, solvent extraction,
ion exchange, chromatography and distillation.
4. The fission products are usually neutron rich and decay by β- emission.
5. Many clinically useful radionuclides such as 131I, 99Mo, 133Xe and 137Cs are
produced by fission of 235U.
6. Two radionuclides, 131I AND 99Mo are of extreme importance in nuclear medicine.
7. The fission radionuclides are normally carrier free or NCA, and therefore isotopes of high
specific activity are available from fission.
● Neutron capture or (n,γ) reaction
● This is one of the most important reactions induced by thermal neutron in the
reactor.
● In this reaction, the target nucleus captures one thermal neutron and emits rays to
produce an isotope of the same element.
● Since the target and the product nuclei belong to the same element, chemical
separation is obviously unnecessary.
● Various useful radionuclides produced by this reaction are 131Te (which produces
131I by β- decay), 99Mo, 197Hg, 59Fe. These radionuclides are often neutron rich
and therefore, decay by β- emission.
● Some examples of neutron capture reactions are
98Mo (n, γ) 99Mo, 196Hg (n, γ)197Hg. 99Mo is not carrier free or NCA type and
therefore has a low specific activity.
 Carrier : A stable element that is added in detectable quantities
to a radionuclide of the same element, usually to facilitate
chemical processing of the radionuclide.
 Carrier-free: (1) Radionuclides produced with atomic
numbers different from those of the target isotopes, do not
contain any stable ( “cold” or “carrier”) isotope detectable by
ordinary analytical methods.
(2) A term used to indicate the absence of any stable atoms
in a radionuclide sample.
 No Carrier Added (NCA): A term used to characterize the state
of a radioactive material to which no stable isotope of the
compound has been added purposely.
Radionuclide production
Specific activity
● Defined as the radioactivity per unit mass of radionuclide, or
labeled compound, (radioactivity/mass, mCi/mg).
● In carrier-free radionuclide, the shorter the half-life, the higher
the specific activity.
Problem
What is the specific activity of carrier-free 111In (t1/2=67 hr)?
Answer :
In 1 mg 111In, the number of atoms N of 111In is
1 X 10-3
N=------------ X 6.02 x 1023
111
The decay constant λ of 111In is
0.693
λ = ------------------- sec-1
67 x 60 x 60
D = Nλ
0.693 x 10-3 x 6.02 x 1023
= --------------------------------- dps
67 x 60 x60 x 111
= 1.56 x 1023 dps
= 4.22 x 105 mCi
Therefore, the specific activity of 111In is 4.22 x 105 mCi/mg or 1.56x104 GBq /
mg.
● The specific activity of a carrier-free or NCA radionuclide can be calculated by
the following formula.
3.13 109
specificactivity(mci / mg ) 
A  t1/ 2
Where A is the mass number of the radionuclide
t1/2 is the half-life in hours of the radionuclide
● The specific activity of a radiopharmaceutical is very important information
for a particular nuclear medicine test. This information is often provided on the
label posted on the vial.
● Low specific activity radionuclide is of little use in some specified labeling
procedures because the cold atoms ( non-radiative) will compete for the binding
sites of the reacting molecules.
.
● High specific activity radionuclide can cause radiolysis in the solution of a
compound, resulting in the breakdown of the compound into undesirable
impurities.
Radiation measurement:
( R) the roentgen for exposure:
Is the amount of x or γ radiation that produces ionization of one electrostatic unit
of either positive or negative charge per cubic centimeter of air at 0 ºC and 760
mmHg.
(rad) radiation absorbed dose is a more universal unit, it is a measure of the energy
deposited in unit mass of any material by any type of radiation. 1 rad = 10-2 J/kg
In SI units, the Gray (Gy) is the unit of radiation absorbed dose and is given by 1 Gy
= 100 rad
(rem) Roentgen equivalent for man has been developed to account for the differences
in effectiveness of different radiations in causing biological damage.
The dose of radiation which produces in man the effects of one rad.
Rem = rad  RBE or QF
RBE is the relative biological effectiveness of the radiation.
In SI units, the dose equivalent is expressed in Sieverts which are defined as 1 Sievert
(Sv) = 100 rem.
Roentegn:
Unit for measuring amount of x or γ rays in air.
Rad:
Unit for measuring absorbed energy from radiation.
When a person is exposed to radiation, energy is deposited in the
tissues of the body. The amount of energy deposited per unit of
weight of human tissue is called the absorbed dose. Absorbed dose is
measured using the conventional rad or the SI Gy.
The rad, which stands for radiation absorbed dose, was the
conventional unit of measurement, but it has been replaced by the
Gy. One Gy is equal to 100 rad.
Rem:
Unit for measuring biological damage from radiattion
Measuring Biological Risk
A person's biological risk (that is, the risk that a person will suffer health effects
from an exposure to radiation) is measured using the conventional unit rem or the
SI unit Sv.