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Compact Neutron Generator
Technology Models: JNG-2-DD/DT
& JNG-3-DD/DT
---Robert Goldstein
Technical Associates,
North American Distributor
OVERHOFF TECHNOLOGY
A Brief Overview
of
Neutron Sources
Naturally Occurring/Environmental Cosmic
The Solar Wind.
High energy charged particles which hit nuclei in the earth’s atmosphere creating secondary particles including neutrons. Intensity varies inversely with solar activity.
Terrestrial Spontaneous fission mostly U-238, less than 10% naturally induced U-235 fission.
A Brief Overview
of
Neutron Sources
Intentional Radioisotope sources
Photoneutron Sources
Accelerator sources
Nuclear reactors
Spallation sources
Neutron generators
A Brief Overview
of
Neutron Sources
Intentional Radioisotope sources
252 Cf SP ½ life 100yr, E(n) 2.3MeV
Table 1.1 Properties of commonly used (ũ,n) sources
Source En (MeV) T 1/2 Yield (n/a)
210Po+BE 5.30 138.4 days 0.7 x 10-4
226Ra+Be 4.78, 4.59 1.622 x 10 3 years 1.8 x 10-4
239Pu+Be 5.15 2.44 x 10 4 years 0.6 x 10-4
241Am+Be 5.48 4.60 x 10 2 years 0.7 x 10-4
242Cm+Be 6.11 163 days 1.1 x 10-4
241Am+B 5.48 2.44 x 10 4 years 1.0 x 10-5
241Am+F 5.48 2.44 x 10 4 years 4.0 x 10-6
A Brief Overview
of
Neutron Sources
Intentional Photoneutron Sources
Table 1.2 Properties of commonly used photoneutron sources
Source En (MeV) T 1/2 Yield (n/s)/ cm 2 gm -1
24Na+Be 2.757 15.1 h 3.8 x 10-6
24Na+D2O 2.757 15.1 h 7.3 x 10-6
72Ga+D2O 2.51 14.3 h 1.9 x 10-6
124Sb+Be 1.691 60.9 days 5.1 x 10-6
140La+Be 2.51 40.2 h 0.08 x 10-6
Radioisotope decay with Gamma energy exceeding the neutron binding
energy of a nucleus can eject a Be or D2 neutron, called a photo-neutron
A Brief Overview
of
Neutron Sources
Intentional Accelerator Sources
The simplest way to use an accelerator to generate neutrons is to use
the bremsstrahlung from electron accelerators such as synchrotron or
beta tron to produce photoneutrons. This gives a continuous energy
distribution which is not very useful.
Pulsed electron linacs can also be used, for example electron
bombardment of Uranium can produce 30MeV neutrons.
A Brief Overview
of
Neutron Sources
Intentional Nuclear Reactors
Nuclear reactor neutrons are ~ 2 MeV plus thermal neutrons plus
moderated higher energy neutrons
Cf-252 has an energy similar to this at 2.35 MeV
The Jiddtek D-D Neutron Generator emits neutrons with similar
energies at ~ 2.45 MeV.
A Brief Overview
of
Neutron Sources
Intentional Spallation sources Are beyond the scope of this presentation.
A Brief Overview
of
Neutron Sources
Intentional Neutron Generators
A subset of the accelerator category which are also
fusion devices.
First used in 1933.
These small electrostatic accelerators use one of two
exothermic reactions (produces energy):
D + 2H --> 3He3 + n 2.35 MeV
D + 3H --> 4He3 + n 14.1 MeV
A Brief Overview
of
Neutron Sources
Intentional Neutron Generators A Metal Hydride Target is Utilized
After the Reaction:
The He and n travel in opposite directions producing high neutron yields.
Energy at different angles is given by:
4En = En d +2(2 En Ed )1/2cos Θ = 3Q
JNG-2 – Neutron Generator
Benefits:
Portability
Reduced Power Input Requirements
Increased Neutron Output
Adaptable for Tailoring to Specific
Customer Needs.
Reduced Manufacturing Costs
High Reliability and Long Operating Life
Applications:
Non-Destructive Testing
Homeland Security / Military
Nuclear Industry
Mining and Drilling
Medicine
Civil, Aeronautical, & Nautical Engineering
Research Laboratories
Typical Target Based Neutron
Generators versus JNG-2
Typical Neutron Generators JNG-2
Design Complicated with Many Electronic and
Physical Components
Simple, mechanically based
Power Consumption Tens of Kilowatts 90 Watts
Neutron Output 10*6 n/s to 10*8 n/s at applied voltages in
the range of hundred kV+
DD – 1*105 n/s
DT – 1*107 n/s
Case Diameter Varies 13 cm
Case Length Varies 65 cm
Weight 33 lbs – 362 lbs 28 lbs
Operation Deuterium – Deuterium – DD
Deuterium – Tritium - DT
Deuterium – Deuterium – DD
Deuterium – Tritium - DT
Projected Lifetime 1,200 hours – 4,000 hours 3-5 Years with Option to Refuel
and Service at End Time
Neutron Generator – Basic Process
Homeland Security / Military
Detection of Explosives & Fissile Material in Cargo or Luggage
Chemical Analysis of Questionable Contents
Land Mine Detection
Shipping Container Evaluation
Narcotics Detection
Nuclear Industry
Compliance with the
GALL Report NUREG-1801 (2010)
Measuring Radiation Structural
Damage
Containment Vessels
Cooling Pools
Pipes
Nuclear Industry
Generic Aging Lessons Learned (GALL)
The GALL report evaluates existing programs for providing structural and component safety in Nuclear Power Plants. As these plants age and come up for renewal the GALL report facilitates the renewal process.
Its focus is on the staff review on the augmented existing programs for license renewal. Incorporation of the GALL report into NUREG-1800 and 1801 improves efficiency of the license renewal process.
Mining & Drilling
Oil Well Logging
On-Line Assaying of Materials i.e. Coal, Cement, etc
Borehole Logging
Fuel Reprocessing
Mining of a Wide Variety of Minerals
Medicine Neutron
Radiography
Neutron Spectroscopy
Neutron Brachytherapy
Boron Neutron Capture Therapy (BNCT)
Civil, Aeronautical, & Nautical Engineering
Structural
Inspection
Gas & Oil Tank
Walls
Bridge Integrity
Airplane/Ship
Components
Piping
Research Laboratories
Material
Science
Nano
Technology
Non-Invasive
Analysis
Specifications for JNG-2 & JNG-3
JNG-2 DD & DT JNG-3 DD & DT
Neutron Output: 105 n/s using D-D
107 n/s using D-T
106 n/s using D-D
108 n/s using D-T
Neutron Energy 2.45 Mev using D-D
14 MeV using D-T
2.45 Mev using D-D
14 MeV using D-T
Cooling System Air Convection Air Convection
Voltage 45kV 65kV
Current 2mA 5mA
Power Consumption 90 W 325 W
Maximum Input Power 250 W 250 W
Length 65 cm 65 cm
Diameter 13 cm 13 cm
Total Weight 13 kg 13 kg
Projected Lifetime 3-5 Years with Option to
Refuel and Service at End
Time
3-5 Years with Option to
Refuel and Service at End
Time
Replaces Need for 252Cf Sources & Other
Radioisotpe Sources
Safer to Operator
Safer to the Public
Eliminates Storage Issues of Source
Material
No risk of theft of radioactive material
Additional Benefits
of the
JNG-2 and JNG-3
Ideal for Calibrating Neutron Detectors for
Spontaneous Fission Neutrons
Calibrate Neutron Detectors for Higher
Energies Including AmBe when Energy
Correction Factor is established
JNG-2-DT Produces 14.1 MeV Neutrons
and is available as a Neutron Interrogator
Certification
This instrument has been tested and
certified by independent university tests at
the University of Sydney, Australia
Further Testing
A Jiddtek D-D neutron generator will be
evaluated at CSU, Fort Collins beginning
this December.
A team from LANL RP-SVS will
participate in that evaluation.
Further Testing
When the higher output D-D generator
becomes available that will be evaluated at
LANL RP-SVS.
The Jiddtek D-D generator will be used
along with RP-SVS’s AmBe and Cf-252
neutron sources to compare neutron energy
responses of a wide range of neutron
detectors
Neutron Generators
Credit for Table 1.1 and 1.2
Neutrons, Nuclei and Matter; An Exploration of
the physics of Slow Neutrons By James Byrne (1994)
Questions and Comments ?
Bob Goldstein, Technical Associates
WWW.TECH-ASSOCIATES.COM
818-883-7043