Abstract

.Cross-sections and their isomeric ratios ( sigma_{mathrm{m}}/sigma_{mathrm{g}}) for the 185Re(n, 2n)184mRe and 185Re(n, 2n)184gRe reactions in the 13–15 MeV range were measured. The neutron activation technique was applied using the K-400 neutron generator at the Chinese Academy of Engineering Physics (CAEP). Natural Re samples and Nb monitor foils were activated jointly to determine the reaction cross-section and the incident neutron flux. The 3H(d, n)4He reaction was used to generate the neutron beam. The pure cross-section of the ground state was derived from the absolute cross-section of the metastable state using residual nuclear decay analysis. Numerical calculations using the nuclear-model-based computer code TALYS-1.8 with six level density models were used to obtain 185Re(n, 2n)184m, gRe reaction excitation functions and their isomeric cross-section ratios. Finally, experimentally determined cross-sections were compared with corresponding literature data.

Highlights

  • Rhenium (Re) metal is a high temperature corrosion resistant material, and its boron-based alloys are effective neutron absorbers used in the regulation of nuclear reactors

  • 14 MeV neutrons can induce a series of nuclear reactions including 185Re(n, 2n)184mRe, 185Re(n, 2n)184gRe and 185Re(n, 2n)184m+gRe, and the related cross-sectional data are of great importance for the evaluation of safety in fusion reactors

  • Cross-sections for the 93Nb(n, 2n)92mNb monitor reaction were taken from ref. [27]

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Summary

Introduction

Rhenium (Re) metal is a high temperature corrosion resistant material, and its boron-based alloys are effective neutron absorbers used in the regulation of nuclear reactors. 14 MeV neutrons can induce a series of nuclear reactions including 185Re(n, 2n)184mRe, 185Re(n, 2n)184gRe and 185Re(n, 2n)184m+gRe, and the related cross-sectional data are of great importance for the evaluation of safety in fusion reactors. They can be used to determine the required treatment of radioactive waste from reactor structural materials and improve radiation protection procedures. The first is related to difference in decay data (i.e., the selection of characteristic rays). 184 Re g 35.4 d and the related decay laws of the produced nuclei to remove the effect of interference reactions and select multiple appropriate characteristic rays.

Material
Neutron energy and irradiation
Gamma spectroscopic measurements
Calculation of cross-sections and their uncertainties
Experimental standard deviation
Nuclear model calculations
Results and discussion
Conclusion
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