Method and portable apparatus for the detection of substances by use of neutron irradiation

• US 5,982,838 A
• Filed: 06/19/1997
• Issued: 11/09/1999
• Est. Priority Date: 03/26/1997
• Status: Expired due to Fees

• Current Assignee: George Vourvopoulos
• Original Assignee: Western Kentucky University
• Inventors: Vourvopoulos, George
• Primary Examiner(s): Wasil, Daniel D.
• Application Number:
  US08/878,938
• Time in Patent Office: 873 Days
• Field of Search: 376/158, 376/159, 376/189, 250/296.6, 250/358.1, 250/390.04, 378/57, 209/589
• US Class Current: 376/159
• CPC Class Codes: G21K 5/04 with beam-forming means

Abstract

The present invention relates to a method and portable apparatus which is used to detect substances, such as explosives and drugs, by neutron irradiation. The apparatus has a portable neutron generating probe and corresponding controllers and data collection computers. The probe emits neutrons in order to interrogate an object. The probe also contains gamma ray detectors for the collection of gamma rays from fast neutron, thermal neutron and neutron activation reactions. Data collected from these detectors is sent to the computer for data de-convolution then object identification in order to determine whether the object being interrogated contains explosives or illicit contraband.

Claims

1. A portable pulsed neutron detection system for detection of specific elements in an object, comprising:

a manually transportable probe, said probe having a pulsed neutron generator and at least one gamma ray detector;

a controller operably connected to said pulsed neutron generator for varying the intensity and pulse characteristics of said pulsed neutron generator so as to emit a beam of neutrons from said generator;

a data acquisition system operably connected to said at least one gamma ray detector for collecting data measured by said detector; and

,

means to analyze said data corresponding to fast neutron reactions, thermal neutron reactions and activation neutron reactions to determine the chemical composition of said object.

2. The system of claim 1 wherein said probe is further comprised of:

a cylindrical housing containing said neutron generator and said at least one gamma ray detector;

shielding material separating said gamma ray detector and said neutron generator.

3. The system of claim 2 wherein said shielding is lead.

4. The system of claim 2 wherein said shielding is bismuth.

5. The system of claim 2 wherein said shielding is positioned around said at least one gamma ray detector about 235 degrees.

6. The system of claim 2 wherein said probe is encased in a stainless steel cylindrical housing.

7. The system of claim 1 wherein said at least one gamma ray detector is bismuth germanate.

8. The system of claim 1 wherein said at least one gamma ray detector is gadolinium orthosilicate.

9. The system of claim 1 wherein said data acquisition system further comprises a computer to process signals supplied by said at least one gamma ray detector.

10. The system of claim 9 wherein said computer generates a fitted spectrum of gamma rays at each energy channel by the equation:

space="preserve" listing-type="equation">f[i]=Σ

.sub.k c.sub.k *m.sub.k [i]+α

*bg[i]

where f is the number of counts in the i-th energy channel of the fitted spectrum, c_k is the multiplication coefficient for the response spectrum of the k-th element, m_k [i] is the number of counts in the i-th channel of the response spectrum of the k-th element, α

is the multiplication coefficient of the background, and bg[i] is the number of counts in the i-th energy channel of the background.

11. The system of claim 10 wherein said m_k [i]'"'"'s are determined by measuring the spectrum of a sample containing only one chemical element.

12. The system of claim 10 wherein said coefficients c_k and α

are determined by the least squares method, minimizing the general X² equation;

space="preserve" listing-type="equation">X.sup.2 =Σ

.sub.i (y.sub.i -f[i]).sup.2 /σ

.sub.i.sup.2

where y_i and σ

_i are the measured counts in the i-th energy channel and the statistical error respectively.

13. The system of claim 1 wherein said controller separates pulses from said neutron generator by between 85 and 90 microseconds.

14. The system of claim 1 wherein said pulsed neutron generator is a deuterium-tritium neutron generator.

15. The system of claim 1 wherein said generator emits neutrons at about 14 MeV.

16. The system of claim 1 wherein said generator produces pulses between about 10 kHz and 14 kHz.

17. The system of claim 1 wherein said at least one gamma ray detector measures fast neutron reactions, thermal neutron reactions and activation neutron reactions.