MEASUREMENT OF THE D-D NEUTRON GENERATION RATE BY PROTON COUNTING

• Kim, In-Jung (Department of Nuclear Engineering, Seoul National University) ;
• Jung, Nam-Suk (Department of Nuclear Engineering, Seoul National University) ;
• Choi, Hee-Dong (Department of Nuclear Engineering, Seoul National University)
• Published : 2008.06.30

Abstract

A detection system was set up to measure the neutron generation rate of a recently developed D-D neutron generator. The system is composed of a Si detector, He-3 detector, and electronics for pulse height analysis. The neutron generation rate was measured by counting protons using the Si detector, and the data was crosschecked by counting neutrons with the He-3 detector. The efficiencies of the Si and He-3 detectors were calibrated independently by using a standard alpha particle source $^{241}Am$ and a bare isotopic neutron source $^{252}Cf$, respectively. The effect of the cross-sectional difference between the D(d,p)T and $D(d,n)^3He$ reactions was evaluated for the case of a thick target. The neutron generation rate was theoretically corrected for the anisotropic emission of protons and neutrons in the D-D reactions. The attenuations of neutron on the path to the He-3 detector by the target assembly and vacuum flange of the neutron generator were considered by the Monte Carlo method using the MCNP 4C2 code. As a result, the neutron generation rate based on the Si detector measurement was determined with a relative uncertainty of ${\pm}5%$, and the two rates measured by both detectors corroborated within 20%.

References

1. I.J. Kim, N.S. Jung, H.D. Jung, Y.S. Hwang and H.D. Choi, 'A D-D Neutron Generator Using a Titanium Drivein Target', Nucl. Instr. and Meth. B, 266, 829 (2008) https://doi.org/10.1016/j.nimb.2008.01.012
2. R. Morrison, Grounding and Shielding Techniques in Instrumentation, 3rd Ed., John Wiley & Sons, New York (1986)
3. J.S. Hendricks, 'MCNP4C2', X-5:RN(U)-JSH-01-01, Memorandum, Los Alamos National Laboratory (2001)
4. Cross Section Evaluation Working Group, 'ENDF/B-VI Summary Documentation', Report BNL-NCS-17541 (ENDF-201), P.R. Rose (Ed.), National Nuclear Data Center, Brookhaven National Laboratory (1991)
5. G.F. Knoll, Radiation Detection and Measurement, 2nd Ed., p. 481, John Wiley & Sons, New York (1989)
6. J.F. Ziegler, 'SRIM-2003', Nucl. Instr. and Meth. B, 219-220, 1027 (2003) https://doi.org/10.1016/j.nimb.2004.01.208
7. G.H. Miley and J. Sved, 'The IEC-A Plasma-target-based Neutron Source', Appl. Radiat. and Isot., 48, 1557 (1997) https://doi.org/10.1016/S0969-8043(97)00257-1
8. J. Csikai, CRC Handbook of Fast Neutron Generators, Vol. 1, p. 99, CRC Press, Inc., Florida (1987)
9. A. Krauss, H.W. Becker, H.P. Trautvetter, C. Rolfs and K. Brand, 'Low-Energy Fusion Cross Sections of D+D and $D+^3$He Reactions', Nucl. Phys. A, 465, 150 (1987) https://doi.org/10.1016/0375-9474(87)90302-2
10. H.H. Barschall, in: A. Michaudon, S. Cierjacks, R.E. Chrien(Eds.), Neutron Sources for Basic Physics and Applications, p. 7, Pergamon Press Ltd., Oxford, 1983
11. J.F. Briesmeister(Ed), 'MCNP - a General Monte Carlo N-particle Transport Code, Version 4C', LA-13709-M, Los Alamos National Laboratory (2000)
12. ORTEC, 'Gamma $Vision^{\circledR}$ 32: Gamma-ray Spectrum Analysis and MCA Emulator for $Microsoft^{\circledR}$ $Windows^{\circledR}$ 95, 98, 2000, and $NT^{\circledR}$', A66-B32 Software User's Manual, Software Version 5.3, USA
13. J. Reijonen, 'Neutron Generators Developed at LBNL for Homeland Security and Imaging Applications', Nucl. Instr. and Meth. B, 261, 272 (2007) https://doi.org/10.1016/j.nimb.2007.04.192
14. J. Kim, 'Neutron Sources Using D-T Mixed Beams Driven into Solid Target', Nucl. Instr. and Meth., 145, 9 (1977) https://doi.org/10.1016/0029-554X(77)90553-5
15. R.L. Hirsch, 'Inertial-Electrostatic Confinement of Ionized Fusion Gases', J. Appl. Phys., 38, 4522 (1967) https://doi.org/10.1063/1.1709162
16. F.E. Cecil and E.B. Nieschmidt, 'Production of 14 MeV Neutrons from D-D Neutron Generators', Nucl. Instr. and Meth. B, 16, 88 (1986) https://doi.org/10.1016/0168-583X(86)90230-2