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Abstract <p>The article presents the results of developing the models and the TRITIUM software module as part of the EUCLID/V2 integrated code for calculating the migration of tritium and other hydrogen isotopes in the primary circuit of lead cooled fast reactors. Tritium is produced in nuclear fuel; it is radioactive in nature and unlike other radionuclides, can penetrate through the fuel pin cladding and primary circuit pipeline walls into the reactor plant (RP) compartments. Hence, it is very important to understand the way in which tritium will behave and propagate to ensure the reactor plant radiation safety. The TRITIUM module incorporates models for the main processes influencing the behavior of hydrogen isotopes in reactor components, including the transfer of isotopes together with the coolant, radioactive decay, penetration through the pipeline walls made of structural materials, degassing from the lead melt, and release of tritium into the reactor plant gaseous loop. To check how correctly the models are implemented in the code by means of software, the article presents the results of verifying the developed module against the data for test problems. The article also presents the code validation results for experiments on the transfer of hydrogen isotopes and their penetration through the pipeline walls made of steels used for the lead cooled reactors designed and constructed in Russia. The presented results demonstrate that the EUCLID/V2 integrated code with the tritium behavior module TRITIUM in the code composition can be used for substantiating the radiation safety of lead cooled reactors and tritium handling systems.</p>

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Models and Validation Results of the TRITIUM Module Used as Part of the EUCLID/V2 Integrated Code for Calculating the Tritium Behavior in Lead Cooled Fast Reactor Systems

  • 期刊论文

  • 发表日期：

    2026年2月1日

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  • M. V. Vorivonchik,
  • D. A. Nazarov,
  • D. S. Sinitsyn,
  • N. A. Mosunova,
  • A. A. Sorokin,
  • A. S. Anikin,
  • A. N. Bukin

摘要

Abstract

The article presents the results of developing the models and the TRITIUM software module as part of the EUCLID/V2 integrated code for calculating the migration of tritium and other hydrogen isotopes in the primary circuit of lead cooled fast reactors. Tritium is produced in nuclear fuel; it is radioactive in nature and unlike other radionuclides, can penetrate through the fuel pin cladding and primary circuit pipeline walls into the reactor plant (RP) compartments. Hence, it is very important to understand the way in which tritium will behave and propagate to ensure the reactor plant radiation safety. The TRITIUM module incorporates models for the main processes influencing the behavior of hydrogen isotopes in reactor components, including the transfer of isotopes together with the coolant, radioactive decay, penetration through the pipeline walls made of structural materials, degassing from the lead melt, and release of tritium into the reactor plant gaseous loop. To check how correctly the models are implemented in the code by means of software, the article presents the results of verifying the developed module against the data for test problems. The article also presents the code validation results for experiments on the transfer of hydrogen isotopes and their penetration through the pipeline walls made of steels used for the lead cooled reactors designed and constructed in Russia. The presented results demonstrate that the EUCLID/V2 integrated code with the tritium behavior module TRITIUM in the code composition can be used for substantiating the radiation safety of lead cooled reactors and tritium handling systems.