A Report On DESIGN OF NEUTRON SOURCES AND INVESTIGATION OF NEUTRON BASED TECHNIQUES FOR THE DETECTION OF EXPLOSIVE MATERIALS

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1 A Report On DESIGN OF NEUTRON SOURCES AND INVESTIGATION OF NEUTRON BASED TECHNIQUES FOR THE DETECTION OF EXPLOSIVE MATERIALS Name of contact person: Surender Kumar Sharma Name of other contributors: R. Shukla, Sijoy C.D, S. Jakhar & A. Shyam Institution: Institute for plasma research, Bhat, Gandhinagar, Gujarat, INDIA Fax:

2 Table of Content 1. Work related to contract performed in the institute during last 3-4 years 2. Scientific scope of project under CRP 3. Detailed work plan for next 18 months 4. Result obtained under CRP till now

3 1. Work related to contract performed in the institute during last 3-4 years Design and development of plasma focus system and its diagnostics A 3.6 kj plasma focus system is designed and developed in the laboratory with anode and cathode diameter of 50mm & 100mm. The inductance of the system is 110nH and short circuit discharge current is 300 ka. The plasma focus is operated with deuterium gas at 0.4 torr and neutrons has been obtained. The diagnostics system of the plasma focus includes rogowski coil for measuring di/dt, neutron detection by bubble detector & silver activation counter and hard X-ray & neutron study by time of flight detector. Design of accelerator based neutron generator Accelerator based neutron generator is designed. The neutron generator uses DT nuclear fusion reaction to produce 14 MeV neutrons. The sub-system of the accelerator based neutron generator includes 2.45 GHz E.C.R Ion source, high voltage power supplies, high voltage platform, acceleration column with beam line & vacuum system and target assembly. The Ion source is working on the test bench and 0.4mA deuterium ion beam current has been extracted from it and focused on the faraday cup. This system is in commissioning stage. Setting up of pulsed neutron generator facility A compact pulsed neutron generator is set up in the laboratory for fast neutron activation for the detection of explosive material by resulting gamma ray analysis. The neutron generator produces the neutron flux of 10 10, 14 MeV neutrons per second. The neutron generator generates monoenergetic 14 MeV neutrons in single shot neutron pulse mode as well as in frequency mode with the neutron pulse repetition rate of 1 Hz to 100 Hz. The neutron generator consists of neutron unit and control unit and it can be started in single start mode and frequency mode with internal or external start. Ammonium nitrate sample has been irradiated with these neutrons and the activation gamma has been measured with the detection system. Neutron diagnostics and detection system Neutron diagnostics has been made for the detection of fast neutron by liquid scintillation detector and its electronics. Bismuth Germanium Orthosilicate (BGO) & Sodium Iodide

4 (NaI) detector has been installed for the detection of gamma ray photon. The detection system also includes multichannel analyzer (MCA), spectroscopic amplifiers and its power supplies. A two channel fast digitizer with sampling rate of 2GSamples per second is also installed for neutron and photon detection system. High purity germanium detector (HPGe) system is under commissioning stage for high-resolution gamma spectroscopy. New neutron building Apart from the existing laboratory a new neutron building has been made for neutronics related experiments. The dimension of the building is 12 m x 6 m x 6 m. 2. Scientific scope of project under CRP Scope of CRP - Detection system for explosive detection experiment and Investigation of neutron based techniques for the detection of explosive material - Design and development of compact and low cost neutron source 3. Detailed work plan for next 18 month - Detection system and Investigation of neutron based techniques for the detection of explosive materials Detection system for explosive detection experiments includes 3 x3 Bismuth Germanium Orthosilicate (BGO) with photo multiplier tube & preamplifier with Canberra make spectroscopy amplifier to detect the γ ray photon generated by activation with fast neutrons. The signal from the amplifier is given to a two channel fast digitizer, Elma make chasis and Gage make digitizer having a maximum sampling rate of 2 GS/second per channel and record length of 16 Mega sample maximum. The signal is transferred through fiber optic cable to personal computer for further processing and analyzing. Pulse height spectrum is done through a dedicate MATLAB routine in which the energy resolution can be kept as per requirement. Ammonium nitrate sample has been irradiated with pulsed neutrons and the pulse height spectrum has been recorded to observe the elemental specific gamma peaks. We have done the qualitative measurement by observing the particular peaks of Nitrogen (N), Oxygen (O) and Hydrogen (H) and we want to do the quantitative measurement to

5 determine the fractional elemental composition and elemental ratio by irradiating sample with fast neutron activation. Prompt gamma signal by the activation of Nitrogen could not be seen so some modification will be done to observe the prompt gamma signal. Irradiation study of other materials will be done and experiments will also be carried out by hiding the sample in a large container. - Design and development compact and low cost of neutron sources A new plasma focus system is designed with specification of 800 Joules, 7.1 microfarad and charged up to 15 kv. The inductance of the system is 25 nh and undamped peak current is 282 ka. The diameter of inner and outer electrode is 1.2 and 2.4 cm. The capacitor bank and its power supply are ready and vacuum of 10-4 is achieved inside the plasma chamber. We will be soon taking the shot with deuterium gas medium. Attempt is also made to make a low cost neutron source using DD nuclear fusion reaction. Some initial experiments were carried out and few neutrons have been also detected. 4. Result obtained till now under CRP 0.5 kg of Ammonium nitrate sample is exposed with single neutron pulse of 14 MeV neutrons with the neutron flux of 10 8 neutrons and neutron pulse with of one microsecond with rise and fall time less than one microsecond. The sample is placed at the distance of 1m from the source and the detector is placed very close to the sample. The shielding of BGO detector against neutron is provided with ultra high-density polyethylene sheets. The γ ray photon emitted by the activation of fast neutron is measured and recorded with the detection system The gamma spectrum of ammonium nitrate is measured and from the observed peak it confirms the presence of Nitrogen (N), Hydrogen (H) and Oxygen (O) in the sample MeV prompt gamma from Nitrogen could not be observed due to saturation of BGO that results in pile up of the gamma ray.

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