Determination of the Deuterium-Tritium (D-T) Generator Neutron Flux using Multi-foil Neutron Activation Analysis Method
The deuterium-tritium (D-T) neutron flux from a Thermo-Fisher™ MP320 neutron generator was determined experimentally in this study. Fast neutron flux from a neutron generator can be measured indirectly using multi-foil activation analysis. Two sets of 12 activation foils each were prepared to cover a broad energy range of fast neutrons (1 – 15 MeV), and spectral peak analysis was performed on each activated foil with a mechanically-cooled HPGe detector. A non-negative solution of a linear least squares problem was solved to find a neutron flux energy distribution. The neutron yields of the high-yield (60 µA-90 kV) and low-yield (30 µA-70 kV) settings were determined to be 1.73×108 n/s and 2.28×107 n/s, respectively. Uncertainties on these neutron yields were estimated using the BC400 scintillator count rates whose fluctuations throughout the irradiations were described by the standard deviations of 10.6 and 8.5%, respectively. Linear relationships between the MP320’s neutron flux and a BC400 scintillator as well as a SWENDI-2 neutron dose meter were also derived to utilize them as on-line neutron flux monitors in the future.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1524045
- Report Number(s):
- INL/EXT-19-53812-Rev000
- Country of Publication:
- United States
- Language:
- English
Similar Records
Measured Thermal And Fast Neutron Fluence Rates ATR Cycle 169A
Measured Thermal and Fact Neutron Fluence Rates for AFC Holders During Cycle 169A