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Prompt GammaRay Imaging for Small Animals

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Absorbed dose for mice. Comparison with MicroPET. 100 uCi 18F is injected into the mouse body ... dose to a 30-gram mouse by PGI (Neutron flux: 108 /cm2 ... – PowerPoint PPT presentation

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Title: Prompt GammaRay Imaging for Small Animals


1
Prompt Gamma-Ray Imagingfor Small Animals
  • Libai Xu
  • Center of Engineering Applications of
    Radioisotopes
  • Department of Nuclear Engineering
  • North Carolina State University
  • Sep. 6th. 2006

2
OUTLINE
  • Introduction
  • System Design
  • Neutron Tomography
  • Prompt Gamma-ray Imaging
  • Some critical questions
  • Absorbed Dose to Small Animals
  • High Energy Prompt Gamma-Ray Detection
  • Conclusions
  • Future work

3
Introduction
  • Overview
  • Literature Reviews
  • Review of small animal imaging
  • Review of in vivo neutron applications
  • Review of prompt gamma imaging

4
Overview
Introduction
  • Prompt Gamma Activation Analysis
  • Identify elements and their abundance
  • Prompt Gamma-ray Imaging
  • Identify elements, abundances, and positions

5
Potential Applications
Introduction
  • NCT (Neutron Capture Therapy) for Cancer
    treatment
  • Selectively deliver 10B or Gd to the tumor
  • Irradiate the tumor region with low energy
    neutrons
  • The short range of the 10B(n,a)7Li reaction
    products restricts most of the dose to the tumor
    cells

?
Coderre, J. A. and Morris, G. M. 1999. The
radiation biology of boron neutron capture
therapy Radiat. Res. 151 1-18
6
System Diagram
Introduction
7
Review of small animal imaging
Introduction
  • Why small animal imaging is important?
  • an non-invasive tool to build animal models of
    human diseases.
  • Save animals, reduce cost
  • Get more complete data, especially for
    longitudinal studies
  • Currently available imaging systems for small
    animals
  • Anatomical Imaging
  • Micro-CT, MRI, Ultrasound
  • Detailed info about tissue structure and
    composition
  • Functional Imaging
  • Micro-PET, Micro-SPECT
  • Spatial distribution or evolution of radio
    nuclides in the body

8
Review of in vivo neutron applications
Introduction
  • PGNAA (Prompt Gamma Neutron Activation Analysis)
  • Human body elemental analysis
  • NCT (Neutron Capture Therapy) for Cancer
    treatment
  • Boron
  • Gd

Coderre, J. A. and Morris, G. M. 1999. The
radiation biology of boron neutron capture
therapy Radiat. Res. 151 1-18
9
Review of prompt gamma-ray imaging
Introduction
  • ?-ray telescope in BNCT
  • Measure Boron distribution

Verbakel, W. F. A. R. et al (1997). A r-ray
telescope for on-line measurements of low boron
concentrations in a head phantom for BNCT.
Nuclear Instruments and Methods in Physics
Research A 394, 163-172
Barker, H. B. and Maier, M. R. (2005). The
STING imaging system based on using neutrons and
gammas. Nuclear Instruments and Methods in
Physics Research A 542, 288-289
10
  • Introduction
  • System Design
  • Neutron Tomography
  • Comparison between X-rays and Neutrons
  • Tomography Simulation
  • Prompt Gamma-ray Imaging
  • System Modeling
  • Imaging
  • Some critical questions
  • Conclusions
  • Future work

11
Comparison between X-rays and Neutrons
Neutron Tomography
  • Neutrons interact with the nuclei of the atoms
  • X-rays interact with the electrons in the shells

Fig. 2-2 Comparison Between X-ray and Neutron
Attenuation
12
Comparison between X-rays and Neutrons
Neutron Tomography
Table 2-1 Attenuation Coefficients of Some
Materials for X-rays and Neutrons
13
Fundamentals of Tomography
Neutron Tomography
System Setup
14
MCNP Simulation
Neutron Tomography
MCNP is used to generate projections
15
Neutron Tomography
A
B
A
B
B
A
A
B
A
B
16
Phantom
Neutron Tomography
17
Neutron Tomography
18
Neutron Tomography
19
Neutron Tomography
20
Neutron Tomography
21
Summary for Neutron Tomography
Neutron Tomography
  • The attenuation coefficient of X-rays is mainly
    determined by object density, but for thermal
    neutrons, it is more related to the hydrogen
    concentration of objects. Totally different
    information is achieved by X-ray imaging and
    neutron imaging.
  • Scattering background is severe in neutron
    tomography. The possible solution is using a
    collimation grid made by a nanotube (Kumakhov,
    2000) to filter the scattered component.

22
System Modeling
Prompt Gamma-ray Imaging
  • Current Available Codes
  • MCNP5
  • CEARCPG
  • GEANT4
  • Requirements for PGI
  • Be capable to simulate coincident gamma rays
  • Be capable to simulate repeated structures
  • 3-D Visualization

23
Neutron Capture Reaction
Prompt Gamma Imaging
12C
13C
24
Prompt Gamma Imaging
25
Hg prompt gamma-ray spectrum
SPECT-like Trial
26
Neutron Capture Reaction by Geant4
Prompt Gamma Imaging
  • Prompt gamma rays are produced in coincidence.
  • 2) Prompt gamma-ray intensity information is
    agreed with ENSDF

27
Prompt Gamma-Ray Yields
Prompt Gamma Imaging
28
Prompt Gamma-Ray Yields
Prompt Gamma Imaging
Capture reactions for each component in soft
tissue (per 1.E6 thermal neutrons)
29
Benchmark Experiments
Prompt Gamma Imaging
  • Pure Hg

30
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31
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32
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33
  • Pure Gd

187kev
785kev
956kev
1190kev
6750kev
34
Prompt Gamma-Ray Imaging
Imaging Methods
  • Mechanical collimations

sample
Detector plane
Pinhole
Coincident detector
35
SPECT-like Trial
36
SPECT-like Trial
37
Projection Images
SPECT-like Trial
370kev prompt gamma rays
38
Prompt Gamma-Ray Imaging
Imaging Methods
  • Electronic collimations

Positron Emission Tomography
39
Angular Correlations
PET-like Trial
Reference Robley D. Evans The Atomic Nucleus
isotropy (a20, a40) co (a21/8,
a41/24) -34 (a2-3, a44).
40
Expectation Maximization
PET-like Trial
The formula for EM algorithm can be derived
(1) Start with o initial estimate ,
satisfying
(2) Iterative function
(3) If the required accuracy for the numerical
convergence has been achieved, then stop.
41
Phantom
PET-like Trial
Radius15cm Width of detector1cm Size of grids
3232 Detector number 32 x (i) i 1, 1024 y (j)
j1,496 a (i, j) Activity ratio of
ABC12.54.5
Where x (i) represents the activity density in
every grid. y (j) represents the observed data in
every detector pair. a (i, j) represents the
probability that one coincident event emitted
from grid x (i) is detected by detector pair
y(j). So known conditions y (j) and a (i, j).
Unknown x (i). Initial starting guess uniform
distribution.
42
Reconstructed Images
PET-like Trial
Phantom
PET
-34
co and isotropy
43
Summary for PGI
  • Geant4 is capable of simulating coincidence gamma
    rays
  • Angular correlations among prompt gamma rays are
    capable of imaging, but only for very strong
    angular correlations such as -34.
  • If not considering the coincidence among prompt
    gamma rays and using the same imaging techniques
    as SPECT, we still could get images

44
  • Introduction
  • System Design
  • Neutron Tomography
  • Prompt Gamma-ray Imaging
  • Some critical questions
  • Absorbed Dose to Small Animals
  • High Energy Prompt Gamma-Ray Detection
  • Conclusions
  • Future Work

45
Absorbed Dose for Mice
  • Method 1

H
C
N
O
MCNP5 and F6 tally
  • A Bozkurt, T C Chao and X G Xu, 2000,
    Fluence-to-dose conversion coefficients from
    monoenergetic neutrons below 20Mev based on the
    VIP-Man anatomical model, Phys. Med. Biol. 45
    3059-3079.

46
Method 2
Absorbed dose for mice
All (n, ?) reactions and 14N(n,p)14C
47
Method 2
Absorbed dose for mice
Step 1 Calculate how many capture reactions
occur for each element. neutron flux,
thermal neutron capture cross section, atom
density are all known
Step 2 Calculate how much energy is
deposited per capture for each element
48
Absorbed dose for mice
Method 2
By (n, ?) capture of H, C, O, and N
By 14N(n,p)14C
The absorbed dose caused by (n, ?) Capture of Hg
is
49
Summary of Results
Absorbed dose for mice
Flux 106 / cm2 s. 30-min scan time
50
Comparison with MicroCT
Absorbed dose for mice
  • According to Chow et al. (2001) the average CT
    dose for a mouse is 10 cGy in a 3-D
    high-resolution X-ray CT system, MicroCAT
    (40kVp/0.500mmAl/250ms/400uA). This dose is
    approximately 1 of LD50/30 for a mouse (9 Gy),
    which is a measure of lethal dose to 50 of the
    population after 30 days.

Reference Chow, P.L., A.L. Goertzen, F. Berger,
J.J. DeMarco, A.F. Chatziioannou, 2001, Monte
Carlo model for estimation of dose delivered to
small animals during 3D high resolution X-ray
computed tomography, Nuclear Science Symposium
Conference Record, 2001 IEEE, Nov. 2001, Vol. 3,
1678-1681.
51
Comparison with MicroPET
Absorbed dose for mice
100 uCi 18F is injected into the mouse body
How much disintegration happens
Absorbed dose caused by one disintegration
Positron 249.8kev/decay Gamma 1022kev/decay
Total Absorbed Dose
52
Comparison with PET/CT
Absorbed dose for mice
  • Absorbed dose in PET/CT
  • CT 40kVp/0.500mmAl/250ms/400uA
  • PET 100 uCi 18F
  • 100 mGy52 mGy152 mGy
  • Absorbed dose in PGI
  • Flux 106 / cm2 s. 30-min scan time
  • 0.8 mGy by body composition
  • 0.55 mGy by 1 Hg

53
Summary for Absorbed Dose
Absorbed dose for mice
  • The absorbed dose to a 30-gram mouse by PGI
    (Neutron flux 108 /cm2 s, 30-min scan time) is
    equivalent to that when the mouse is scanned by a
    combined PET/CT system (CT40kVp/0.500mmAl/250ms/4
    00uA, PET 100 uCi 18F).

54
High Energy Prompt Gamma-Ray Detection
  • The common prompt gamma-ray energy range is from
    several kev to 11Mev.
  • Pair production will be dominant for high energy
    gamma ray.
  • Typical size of MicroPET scanners is 2mm2mm10mm
  • 1Mev electron has 1mm range in LSO crystal
  • Angular distribution of pair production is
    isotropic or forward?

55
MCNP5
High energy ? detection
Robley D. Evans, The Atomic Nucleus, McGRAW-Hill
Book Company, London, 1955.
56
Results
High energy ? detection
57
Comparison between Isotropic and Actual Forward
Angular Distributions
High energy ? detection
58
Detection efficiency for 2mm2mm10mm
High energy ? detection
59
Detection Efficiencies for Various LSO Detector
Sizes
High energy ? detection
60
Summary for High Energy r Detection
  • Detection with small LSO crystals for imaging
    applications is adequate for low- and high-energy
    gamma rays where either the photoelectric or pair
    production interactions dominate, but not as well
    for the intermediate range of gamma rays where
    the Compton scatter interaction dominates.

61
  • Introduction
  • System Design
  • Neutron Tomography
  • Prompt Gamma-ray Imaging
  • Some critical questions
  • Absorbed Dose to Small Animals
  • High Energy Prompt Gamma-Ray Detection
  • Conclusions
  • Future Work

62
Conclusions
  • 1. From the aspect of imaging, the angular
    correlations among prompt gamma rays are capable
    of imaging, but only for very strong angular
    correlations such as -34. If not considering
    the coincidence among prompt gamma rays and using
    the same imaging techniques as SPECT, we could
    get images. However, the new problem is that
    gamma-ray energy here is much higher than that in
    SPECT. New features of collimators are required
    to solve this problem.

63
Conclusions
  • 2. From the aspect of radiation dose to small
    animals, the equivalent dose for a mouse when
    imaged with a thermal neutron beam with a flux of
    10 8/ cm 2 s in 30 minutes will be equivalent to
    that when imaged with a combined PET/CT system
    (For CT, 40kVp/0.500mmAl/250ms/400uA and For PET,
    100uCi 18F).

64
Conclusions
  • 3. From the aspect of gamma-ray yields, the
    gamma-ray yields are low for most elements in the
    normal concentrations. It indicates that PGI is
    not a general application for all elements. Only
    some elements with very high cross section are
    suitable, such as Hg, Cd, Gd, et al. Or in
    certain cases, the concentrations of elements are
    very high and their cross sections are not very
    small, such as H in organic body, and B in BNCT.

65
Future Work
  • Variance reduction techniques for Geant4
  • Nuclear data libraries, especially for nuclear
    structure data
  • Nanotube may be utilized as collimation grids and
    to reduce scattered neutron background
  • More accurate voxel-based mouse phantom

66
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