Passive Neutron Multiplicity Device for 240Pu Measurement Based on FPGA
Passive Neutron Multiplicity Device for 240Pu Measurement Based on FPGA
passive neutron multiplicity measurement device, FH-NCM/S1, based on field-programmable gate arrays<br />(FPGAs), is developed specifically for measuring the mass of plutonium-240 (240Pu) in mixed oxide fuel. FHNCM/<br />S1 adopts an integrated approach, combining the shift-register analysis mode with the pulse-position<br />timestamp mode using an FPGA. The optimal effective length of the 3He neutron detector was determined to<br />be 30 cm, and the thickness of the graphite reflector was ascertained to be 15 cm through MCNP simulations.<br />After fabricating the device, calibration measurements were performed using a 252Cf neutron source; a detection<br />efficiency of 43.07% and detector die-away time of 55.79 μs were observed. Nine samples of plutonium<br />oxide were measured under identical conditions using the FH-NCM/S1 in shift-register analysis mode and a<br />plutonium-waste multiplicity counter. The obtained double rates underwent corrections for detection efficiency<br />(ε) and double gate fraction (f d), resulting in corrected double rates (Dc), which were used to validate the accuracy<br />of the shift-register analysis mode. Furthermore, the device exhibited fluctuations in the measurement<br />results, and within a single 20-s measurement, these fluctuations remained below 10%. After 30 cycles, the<br />relative error in the mass of 240Pu was less than 5%. Finally, correlation calculations confirmed the robust<br />consistency of both measurement modes. This study holds specific significance for the subsequent design and<br />development of neutron multiplicity devices.
passive neutron multiplicity measurement device, FH-NCM/S1, based on field-programmable gate arrays (FPGAs), is developed specifically for measuring the mass of plutonium-240 (240Pu) in mixed oxide fuel. FHNCM/S1 adopts an integrated approach, combining the shift-register analysis mode with the pulse-position timestamp mode using an FPGA. The optimal effective length of the 3He neutron detector was determined to be 30 cm, and the thickness of the graphite reflector was ascertained to be 15 cm through MCNP simulations. After fabricating the device, calibration measurements were performed using a 252Cf neutron source; a detection efficiency of 43.07% and detector die-away time of 55.79 s were observed. Nine samples of plutonium oxide were measured under identical conditions using the FH-NCM/S1 in shift-register analysis mode and a plutonium-waste multiplicity counter. The obtained double rates underwent corrections for detection efficiency() and double gate fraction (f d), resulting in corrected double rates (Dc), which were used to validate the accuracy of the shift-register analysis mode. Furthermore, the device exhibited fluctuations in the measurement results, and within a single 20-s measurement, these fluctuations remained below 10%. After 30 cycles, the relative error in the mass of 240Pu was less than 5%. Finally, correlation calculations confirmed the robust consistency of both measurement modes. This study holds specific significance for the subsequent design and development of neutron multiplicity devices.
粒子探测技术、辐射探测技术、核仪器仪表核燃料、核燃料生产
Spent fuelNon-destructive assayNeutron multiplicity240PuFPGA
Spent fuelNon-destructive assayNeutron multiplicity240PuFPGA
.Passive Neutron Multiplicity Device for 240Pu Measurement Based on FPGA[EB/OL].(2024-05-17)[2025-04-30].https://chinaxiv.org/abs/202405.00248.点此复制
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