Neutrons have been utilized for several decades to measure elements.
In oil exploration, the carbon/oxygen ratio (C/O) is a measure of
oil saturation
[i].
In the coal industry,
elements such as sulfur and chlorine are
routinely measured with neutron interrogation
[ii] ,
[iii]
In the airline industry, the inspection of checked luggage for high
explosives has been proposed through the use of neutrons for the
identification of the nitrogen content within a piece of luggage
[iv].
Neutron-based systems have also been proposed for the
detection
of narcotics and other contraband
[v]
,
[vi]
by the measurement of
C/O.
The physical principles that all these methods
are based upon have been established for a number of years, and have
been extensively used by nuclear physicists and chemists for the
investigation of nuclear structure.
Figure 1. Nuclear reactions initiated by thermal neutrons (capture reactions)
and fast neutrons (inelastic scattering).
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In principle, a neutron impinging on an object
can initiate one of several nuclear reactions with the chemical
elements of which the object is composed (Figure 1). In most of
these cases, as a result of these reactions, γ-rays are emitted with
characteristic and distinct energies. These γ-rays are like the
“fingerprints” of the elements contained in the object. By counting
the number of γ-rays
emitted with a specific energy (e.g. the γ-rays of sulfur), one can
deduce the amount of the element contained within the object. In
the case of an object that is hidden among other innocuous
materials, the identification takes place through the correlation of
various chemical elements observed, coupled to the information about
the innocuous material itself.
Neutrons are highly penetrating particles.
Their intensity is not diminished by the thickness of common
containers. To a lesser extent, the outgoing γ-rays are also very
penetrating, easily exiting the interrogated volume to be detected
by an appropriate set of detectors placed outside the object. Thus,
the method is non-intrusive (the interrogation can take place from a
distance of several centimeters) and non-destructive because of the
very small amount of radiation absorbed by the interrogated object.
Depending on the chemical elements that one
wishes to measure, one might have to use neutrons of several
energies. In many of the neutron-based applications currently in
use, radioisotopic sources (Am-Be, 252Cf) are utilized
for neutron production. These sources can excite a host of chemical
elements (H, C, S, Fe, etc.) through neutron capture reactions.
However, there are other elements such as C and O which need neutron
energies several MeV higher than those available from the
radioactive sources. To satisfy this, a neutron source is required
that can produce the high energy neutrons for measurement of
elements such as C and O, and low energy (0.025 eV) for elements
such as H and Cl. It has been shown
[vii],
[viii]
that such a task can be accomplished with the utilization of a
pulsed neutron generator. This technique is called Pulsed
Fast / Thermal Neutron Analysis (PFTNA).
The basis of PFTNA is a pulsed neutron
generator utilizing the deuterium-tritium (d-T) reaction. The
pulsed d-T neutron generator provides 14 MeV neutrons which in turn
initiate several types of nuclear reactions ((n,n'γ), (n,pγ), (n,γ)
etc.) on the object under scrutiny.The γ-rays from these reactions
are detected by a suitable set of detectors (usually bismuth germanate (BGO) scintillators).
During the neutron pulse, the
γ-ray spectrum is primarily
composed of
γ-rays from the
(n,n’γ) and (n,pγ)
reactions on elements such as C and O, and is stored at a
particular memory location within the data acquisition system.
Between pulses, some of the fast neutrons that are still within the
object lose energy by collisions with light elements composing the
object. When the neutrons have an energy less than 1 eV, they are
captured by such elements as H, N, and Fe through (n, γ) reactions. The
γ-rays from this set of reactions are detected by the same set of
detectors but stored at a different memory address within the data
acquisition system. This procedure is repeated with a frequency of
approximately 10 kHz. After a predetermined number of pulses, there
is a longer pause that allows the detection of γ-rays emitted from elements
such as Si and P that have been activated. Therefore, by utilizing
fast neutron reactions, neutron capture reactions, and activation
analysis, a large number of elements contained in an object can be
identified in a continuous mode without sampling. Figure 2 shows
the time sequence of the nuclear reactions taking place.
Figure 2. Pulsed neutron generator time sequence.
|
PFTNA uses low resolution, high Z detectors
such as bismuth germanate (BGO) or gadolinium ortho-silicate (GSO).
Data analysis of the resulting γ-ray
spectra is performed with the computer code SPIDER, a spectrum
deconvolution code developed for the Windows 95/98/NT platforms
[ix]
.
This code has been updated for use with the Windows 2000/XP
platforms as well.
To use SPIDER, one must first measure the
response of the detector in question to γ-rays from pure elements.
For example, a block of pure graphite is used to determine the
detector’s response to the C γ-rays.
To determine the detector’s response to elemental H, a response is
measured from a water sample.
In the absence of any sample placed in front of
the detector, the detector records
γ-rays emanating from the materials surrounding the detector,
as well as from the materials inside and around the neutron
generator. This spectrum is called the background spectrum. The
counts in the ith channel of the spectrum of a
sample, S, can be represented by the equation:
(1)
where Bi is the background
spectrum at the ith channel and k is its
coefficient, Ei,j is the response of the jth
element at the ith channel and cj
is its coefficient, and n is the total number of elements
utilized to fit the spectrum. SPIDER employs a least-squares
algorithm to fit Equation (1).
Primarily, identification of a substance by
PFTNA is performed through examining the atomic ratios, e.g. the
ratio of carbon atoms to oxygen atoms (C/O). The measurement of C/O
is performed by taking the ratio of the intensities for carbon and
oxygen γ-rays and then
applying the ratio of the (n,n'γ)
cross-sections for these elements.
In previous papers
[x]
,
[xi],
the accuracy and precision of a measurement with PFTNA was
examined. It was found that measurements could be performed with a
PFTNA-based system as quickly as 30 s. However, more precise
results are achieved at 300 s. The time of 300 s seems to be
optimal since measuring for longer periods does not significantly
reduce measurement uncertainties. Also, the measurement
uncertainty is not affected greatly by the acquisition time of the
background spectrum used in Equation 1.
The precision of the PFTNA-based system
configured with a BGO detector was found to be about 5%. The accuracy with this
detector ranged between 2 and 12%. This accuracy and precision is
equivalent to those published in Reference 11
that utilized a GSO detector. The advantage in
using BGO instead of a GSO detector is its lower price and higher
efficiency.
[i] H. D. Scot, C. Stoller, B. A. Roscoe, R. E. Plasek, and R.
Adolph, A New Compensated Through-Tubing Carbon/Oxygen Tool for
Use in Flowing Wells in Trans. Of the SPWLA 32nd
Annual Logging Symposium, Midland TX, June 1991, paper MM.
[ii]
A. T. Kirchner, IAE Coal Research 40, London, UK, Sept. 1991
[iii] L. Dep, M. Belbot, G. Vourvopoulos, and S. Sudar,
J. of Radioanal. and Nucl. Chem., Vol. 234, Nos. 1-2 (1998)
107-112.
[iv]
Symposium on Explosive Detection Technology, S. Khan,
Ed., Atlantic City, NJ, 1991.
[v] D. R. Brown and T. Gozani, NIM B 99, 1995, p. 753-756.
[vi] G. Vourvopoulos, and J. Thornton, A Transportable,
Neutron-Based Contraband Detection System in Proc. of Counterdrug Law Enforcement: Applied Technology for Improved
Operational Effectiveness, Nashua, NH, p.2-39, 1995.
[vii] G. Vourvopoulos, F. J. Schultz, and J. Kehayias, A Pulsed
Fast/Thermal Neutron Interrogation System in Symp. on
Explosive Detection Technology, Ed. S. Khan, FAA Technical Center, Atlantic City, 1991, p.27.
[viii]
P. C. Womble, F. J. Schultz, and G. Vourvopoulos, NIM B 99, 1995, p. 757.
[ix] G. Vourvopoulos, L. Dep, S. Sudar, P. C. Womble, and F. J.
Schultz, Neutron-Generator Based On-Line Coal Analysis: A
Progress Report in Proc. 8th Int’l Conf. On Coal Science, Eds.
J.A. Pajares and J.M.D. Tascon, Elsevier Science B. V., Oviedo,
Spain, 1995.
[x] P. C.
Womble, G. Vourvopoulos, J. Ball Howard and J. Paschal,
Neutron-Based Portable Drug Probe in Proc. Of 15th International
Conference on the Applications of Accelerators in Research and
Industry, Denton TX, AIP Press, 1999, p.
691.
[xi] P. C. Womble, G. Vourvopoulos, P. A. Dokhale, J. Ball Howard and
J. Paschal, Neutron-Based Portable Drug Probe in Proc. Of
Counterdrug Law Enforcement: Applied Technology for Improved
Operational Effectiveness, Washington, D.C., In Press, 1999.
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