sodium iodide detector

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  • 7/31/2019 Sodium Iodide Detector

    1/1

    Nuclear Counting Laboratory

    Sodium Iodide NaI(Tl) Scintillation Detector

    By: E.S. Krage

    Department of Physics, South Dakota State University, Brookings, SD 57007.

    Radioactivity is a process where an unstable nucleus will

    adjust itself until it is stable either by ejecting portions of its

    nucleus or by emitting energy in the form of photons

    (gamma rays).

    Sodium Iodide (NaI) is a type of scintillation detector that is

    able to detect these forms of radioactive decay.

    The scintillation detector was developed by Sir Samuel

    Curran in 1944 while working on the Manhattan Project.

    These detectors are used every day in many places such as nuclear

    power plants national labs and any other place that is concerned with

    radiation effects.

    Some highlights of what they are being used for today

    environmental assay of the Fukushima power plant and how

    radionuclides are being deposited throughout the world.

    Scintillation detectors are used as a form of spectroscopy to analyze

    elemental composition through neutron activation analysis.

    Carbon dating can use scintillation detectors to age archeological

    artifacts.

    A combination of multiple detectors can be used to create medical

    images.

    BACKGROUND

    ANALYSIS

    EFFICENCIES

    APPLICATIONS

    CONTACT

    BASIC PRINCIPAL CONTINUED

    BASIC PRINCIPAL

    The Sodium Iodide detector is a form of scintillation

    detector. The basic principal is the use of a crystal (Sodium

    Iodide) which will emit photons (scintillates) when

    interacting with radiation.

    While the Sodium Iodide is the most common type of

    material used there are many other forms available.

    In general the light produced from the scintillating material

    travels through a window where it gets transferred into adevice called a photomultiplier tube (pmt). A photomultiplier

    tube is made up of components called photocathode,

    dynodes and an anode.

    The photons strike the photocathode and in turn it produces

    electrons. These electrons are then pulled to a series of

    dynodes through the amplification of a positive high voltage.

    When the electrons from the photocathode hit the first

    dynode, several electrons are produced for each incident

    electron.

    These many electrons are now pulled to another dynode and

    the process repeats until it reaches anode. At the time it

    reaches the anode the volume of electrons is much greater

    than initially incident on the detector. When the electrons are

    connected they form a pulse this pulse is further analyzed to

    determine needed information.

    PMT

    Incident

    Radiation

    NaIThallium Excited Atom

    Electron Given

    off

    Photon

    From Tl

    PMT

    DynodesCathode

    Anode

    Solid Scintillation

    In solid scintillation an incident beam of radiation in this case gamma rays comes in and interacts with the Tl doped NaI

    and ionizes the Tl.

    Then in the process of de-excitation a photon will be produced that can be measured by the pmt.

    Summarizing the mechanisms of photon emission subsequent to electron-hole production in the NaI(Tl) crystal can occur

    in the following two sequences electron hole trapping and radioactive recombination mechanisms.

    Electron hole reaction is the majority of the mechanism by which we measure scintillation.

    The Tl is normally found in the crystal lattice as Ti+ ions. Electrons, e-, are trapped by the Tl+ to form T10 by +Tl+Tl

    Tl0 and h++ Tl+ Tl++

    The second method is the recombination method where holes are tryapped by the Tl+ to form Tl++. When added to the

    high voltage we have e - + Tl++ Tl+ + (a photon between 335 to 420nm) this photon is then captured by the pmt.

    From the pmt the signal will be analyzed using a multi channel analyzer which automatically separates the counts based on

    the amount of energy contained in the incident photon.

    The accuracy of separating the different energies is dependent on the type and efficiency of detector. Figure 2 shows the ideal

    peaks that we would desire for a scintillation detector and what we actually get using a NaI(Tl) detector.

    Imperfections in the crystal and circuitry lead to the blurring of the photopeak.

    The energy the photopeak occurs at can be matched up to a specific nuclide and

    identified.

    In the case of Cs137 it has a gamma () decay of 661.65 KeV in the spectrum

    below we can analyze and find what elements we have present.

    Energy

    C

    o

    u

    n

    t

    s

    661.7 Kev

    Cs137

    1.17 MeV 1.33 MeV

    Co60 Peaks

    Compton

    Valley

    Compton

    Peak

    Compton

    Plateau

    Figure 2: The difference between the ideal photopeak and the true photopeak.

    Figure 1: The incident radiation excites the hole and then it gives off

    an electron and a photon from the Tl which can be then analyzed by

    the pmt base.

    Pmt Base

    Figure 3: Screen shot using Cs137 and Co60 test sources using NaI(Tl)

    detector serial no. 895

    In Figure 3. we observe the effects of Compton peak, Compton

    peak, and Compton valley.

    In Compton scattering the incident photon transfers part of its

    energy to an outer shell or a free electron, ejecting it from

    the atom. Upon ejection this electron is called a Compton

    electron.

    If both the Compton electron and deflected photon are

    detected their total energy will equal that of the incident

    photon and the event will register in the photopeak.

    Often the photon escapes detection, so that the event deposits

    only the energy of the Compton electron producing a reduced

    peak value.

    The Compton valley sum energy of multiple Compton

    electrons created by one incident photon.

    The Compton plateau refers to the energies that are less than

    the Compton peak.

    The fundamental meaning of efficiency in nuclear counting

    is the amount observed as a fraction of the amount

    expected. The overall efficiency of a detector can be

    considered in terms of intrinsic and geometric efficiency.

    Geometric efficiency is the measure of the number of

    photons striking the face of the detector compared to

    partial interactions of the lack of interactions due to

    radioactivity being emminated in all directions.

    The intrinsic efficiency can be calculated if a known

    source emitting a known number of photons is placed

    directly against the face of the detector. In this

    arrangement geometric factors can be ignored.

    There are two different types of detectors flat and well

    detectors.

    The flat detector in Figure 4 is considered to be a 1-Defficiency only capturing incident radiation in on

    direction.

    The well detector in Figure 5 is a 3-D detector because of

    its ability to capture incident photons in 3 directions.

    Figure 5: Flat NaI Detector Figure 6: Well NaI Detector

    Dr. Robert McTaggartAssociate Professor of Physics

    Coordinator of Nuclear Education

    South Dakota State University

    President, North Central Chapter of the Health Physics Society

    (605) 688-6306