Boron loaded plastic scintillator could detect both fast neutrons (thanks to hydrogen) and slow neutrons (thanks to 10B). The large cross sections of both reactions lead to high detection efficiency of incident neutrons. However, gamma rays must be rejected first as the scintillator is also sensitive to them. In the present research zero crossing method was used to test neutron-gamma discrimination performance of BC454 boron loaded plastic scintillator. Three contrast experiments were carried out and different thermalization degrees lead to different time spectra in the MCA. Further analysis proved that three Gaussian curves could be used to fit the spectra; they corresponded to gamma rays, fast neutrons and slow neutrons respectively. The slow neutron curve could be clearly separated from the gamma curve. Discrimination performance for fast neutrons became poor, but their peaks could also be separated.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4931-6
PROCEEDINGS PAPER
Neutron-Gamma Discrimination Using Zero-Crossing Method for BC454 Boron Loaded Plastic Scintillator
Dong Wang,
Dong Wang
Xi’an Research Inst. of Hi-Tech, Xi’an, Shannxi, China
Search for other works by this author on:
Bin He,
Bin He
Xi’an Research Inst. of Hi-Tech, Xi’an, Shannxi, China
Search for other works by this author on:
Quanhu Zhang
Quanhu Zhang
Xi’an Research Inst. of Hi-Tech, Xi’an, Shannxi, China
Search for other works by this author on:
Dong Wang
Xi’an Research Inst. of Hi-Tech, Xi’an, Shannxi, China
Bin He
Xi’an Research Inst. of Hi-Tech, Xi’an, Shannxi, China
Quanhu Zhang
Xi’an Research Inst. of Hi-Tech, Xi’an, Shannxi, China
Paper No:
ICONE18-29223, pp. 89-92; 4 pages
Published Online:
April 8, 2011
Citation
Wang, D, He, B, & Zhang, Q. "Neutron-Gamma Discrimination Using Zero-Crossing Method for BC454 Boron Loaded Plastic Scintillator." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 3. Xi’an, China. May 17–21, 2010. pp. 89-92. ASME. https://doi.org/10.1115/ICONE18-29223
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites
ASME J of Nuclear Rad Sci (January,2023)
Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System
ASME J of Nuclear Rad Sci (October,2022)
Measurement of Selected Differential Cross Sections in 235 U Spectrum
ASME J of Nuclear Rad Sci (July,2019)
Related Chapters
Study of the Diffusible Hydrogen in Aluminized Boron Steel
International Hydrogen Conference (IHC 2016): Materials Performance in Hydrogen Environments
Radial Delayed Hydride Cracking in Irradiated Zircaloy-2 Cladding: Advanced Characterization Techniques
Zirconium in the Nuclear Industry: 20th International Symposium
In situ Neutron Transmission Bragg Edge Measurements of Strain Fields near Fatigue Cracks Grown in Air and in Hydrogen
International Hydrogen Conference (IHC 2016): Materials Performance in Hydrogen Environments