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<p>This study investigates the effect of fast neutron irradiation on the electrical resistivity of 12KH18H10T austenitic stainless steel under conditions simulating reactor nominal power. Austenitic steels are widely used in nuclear reactor cores and fuel claddings due to their low induced radioactivity and high resistance to radiation swelling and creep. However, their electrophysical properties under high-fluence neutron exposure remain insufficiently studied, particularly in in situ mode. An experimental setup was developed and installed in the second vertical channel of the VVR-SM research reactor (Institute of Nuclear Physics, Uzbekistan) to enable in situ four-probe electrical resistance measurements during irradiation. Samples of 12KH18H10T steel (13 × 1 × 41&#xa0;mm plates) were irradiated with fast neutrons (E &gt; 0.1&#xa0;MeV) at a flux density of 3.95·10¹² cm⁻²·s⁻¹. The neutron fluence ranged from 2.84·10¹⁶ to 1.65·10¹⁸ cm⁻². The temperature was maintained at 318&#xa0;K, and a type K thermocouple was used for continuous monitoring. The results revealed a non-monotonic dependence of electrical resistance on neutron fluence. At low fluences (up to ~ 2.84·10¹⁷ cm⁻²), resistance increased sharply, attributed to the accumulation of point defects and dislocations in the crystal lattice. After reaching a threshold fluence of approximately 6.73·10¹⁷ cm⁻², a pronounced decrease in resistance was observed, indicating the onset of radiation-induced defect annealing. At higher fluences (above 1.33·10¹⁸ cm⁻²), resistance stabilized, suggesting a dynamic equilibrium between defect generation and annihilation. These findings demonstrate that in situ electrical resistance monitoring is a sensitive and reliable tool for detecting microstructural changes in reactor structural materials. The method enables real-time assessment of radiation damage kinetics and can be applied for operational diagnostics in nuclear facilities. Resistivity measurements can be used as a non-destructive assessment method for monitoring the of irradiation-induced damage to steel during the operation of nuclear reactors [1].</p>

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Change in electrical resistance of 12KH18H10T steel depending on the fast neutron fluence at reactor nominal power

  • 期刊论文

  • 发表日期：

    2026年7月15日

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  • Ilkham Sadikov,
  • Fakhrulla Kungurov,
  • Sapar Baytelesov,
  • Sherali Alikulov,
  • Diyer Tadjibaev

摘要

This study investigates the effect of fast neutron irradiation on the electrical resistivity of 12KH18H10T austenitic stainless steel under conditions simulating reactor nominal power. Austenitic steels are widely used in nuclear reactor cores and fuel claddings due to their low induced radioactivity and high resistance to radiation swelling and creep. However, their electrophysical properties under high-fluence neutron exposure remain insufficiently studied, particularly in in situ mode. An experimental setup was developed and installed in the second vertical channel of the VVR-SM research reactor (Institute of Nuclear Physics, Uzbekistan) to enable in situ four-probe electrical resistance measurements during irradiation. Samples of 12KH18H10T steel (13 × 1 × 41 mm plates) were irradiated with fast neutrons (E > 0.1 MeV) at a flux density of 3.95·10¹² cm⁻²·s⁻¹. The neutron fluence ranged from 2.84·10¹⁶ to 1.65·10¹⁸ cm⁻². The temperature was maintained at 318 K, and a type K thermocouple was used for continuous monitoring. The results revealed a non-monotonic dependence of electrical resistance on neutron fluence. At low fluences (up to ~ 2.84·10¹⁷ cm⁻²), resistance increased sharply, attributed to the accumulation of point defects and dislocations in the crystal lattice. After reaching a threshold fluence of approximately 6.73·10¹⁷ cm⁻², a pronounced decrease in resistance was observed, indicating the onset of radiation-induced defect annealing. At higher fluences (above 1.33·10¹⁸ cm⁻²), resistance stabilized, suggesting a dynamic equilibrium between defect generation and annihilation. These findings demonstrate that in situ electrical resistance monitoring is a sensitive and reliable tool for detecting microstructural changes in reactor structural materials. The method enables real-time assessment of radiation damage kinetics and can be applied for operational diagnostics in nuclear facilities. Resistivity measurements can be used as a non-destructive assessment method for monitoring the of irradiation-induced damage to steel during the operation of nuclear reactors [1].