Abstract

The idea of the first method is to search the neutron energy for the ratio of fission cross section to capture cross section of the selected actinide isotope from the nuclear data base that is equal to the measured ratio of the fissioned and captured actinide isotope Np-237.The idea of the second method consists in the measurement of the reverse dark current increase, which is linearly proportional to neutron fluence, induced by the fast neutron irradiation in planar silicon detectors.Np-237 samples and planar silicon detectors were placed inside a subcritical assembly (the Quinta assembly at the Joint Institute for Nuclear Research, Russia) very close to each other assuming that in both samples the same neutron fluence should pass.We concluded that minor actinide samples and planar silicon detectors can be used as neutron fluence detectors especially in the high neutron energy range, where measurements are difficult.Considering the importance of high energy neutron measurement in the ADS (Accelerator Driven System), actinide and silicon detectors could be a very useful tool.

Highlights

  • Minor actinides (MA) (Np, Am, Cm) are generated in nuclear fuel during irradiation in a reactor

  • This in turn implies that the calibration of the silicon detector with a neutron flux of any energy from this range is fulfilled within accuracy of 25%

  • Performing an experimental study of transmutation of actinides in a deeply sub-critical assembly controlled by an external neutron source (ADS) - the Quinta assembly, we proposed minor actinide application as a neutron fluence and average neutron energy detector in the place of their location in order to determine the optimal place in the accelerator driven systems (ADS) for the incineration of the actinides [3]

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Summary

Introduction

Minor actinides (MA) (Np, Am, Cm) are generated in nuclear fuel during irradiation in a reactor These elements significantly contribute in radio-toxicity and heat generation of spent nuclear fuel. The key issue for reducing the MA radio-toxicity is the partitioning and transmutation of MA in fast neutron reactors (FR) or accelerator driven systems (ADS). The problem is to determine the optimal place in the ADS for incineration of actinides. This can be done by application of actinides and silicon semiconductors as detectors of fast neutron fluence. The Quinta experimental assembly simulating a deeply sub-critical assembly, located at the Joint Institute for Nuclear Research (JINR), Dubna, Russia, was used for preliminary application of the fast neutron spectrum to the actinides and silicon semiconductors to study the neutron fluence. The Quinta target was irradiated with a pulsed proton extracted from the Phasotron accelerator

Actinide fast neutron fluence measurement method
Silicon semiconductor fast neutron fluence measurement method
Motivation of comparison of the two fast neutron fluence measurement methods
The Quinta assembly
Principles of the measurements
Irradiation details
Findings
Discussion
Conclusion

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