A detailed investigation of interactions within the shielding to HPGe detector response using MCNP code
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T. T. Thanh
Abstract
The accuracy of the coincidence-summing corrections in gamma spectrometry depends on the total efficiency calibration that is hardly obtained over the whole energy as the required experimental conditions are not easily attained. Monte Carlo simulations using MCNP5 code was performed in order to estimate the affect of the shielding to total efficiency. The effect of HPGe response are also shown.
References
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© 2012, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Remarks on boiling water reactor stability analysis – part 2: stability monitoring
- Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti
- Heat transfer study of a submerged reactor channel under boil-off condition
- Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method
- Effect of using FLiBe and FLiNaBe molten salts bearing plutonium fluorides on the neutronic performance of PACER
- Evaluations of the CCFL and critical flow models in TRACE for PWR LBLOCA analysis
- Development of program DETSIM to simulate detector's full energy peak efficiency
- The criticality calculations for one-speed neutrons in a reflected slab with anisotropic scattering using the modified UN method
- A detailed investigation of interactions within the shielding to HPGe detector response using MCNP code
- Cosmic ray angular distribution employing plastic scintillation detectors and flash-ADC/FPGA-based readout systems
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Remarks on boiling water reactor stability analysis – part 2: stability monitoring
- Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti
- Heat transfer study of a submerged reactor channel under boil-off condition
- Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method
- Effect of using FLiBe and FLiNaBe molten salts bearing plutonium fluorides on the neutronic performance of PACER
- Evaluations of the CCFL and critical flow models in TRACE for PWR LBLOCA analysis
- Development of program DETSIM to simulate detector's full energy peak efficiency
- The criticality calculations for one-speed neutrons in a reflected slab with anisotropic scattering using the modified UN method
- A detailed investigation of interactions within the shielding to HPGe detector response using MCNP code
- Cosmic ray angular distribution employing plastic scintillation detectors and flash-ADC/FPGA-based readout systems
