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Inventories of Short-Lived Fission Gas Nuclides in Nuclear Reactors

Author

Listed:
  • Yu Wang

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

  • Jianzhu Cao

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

  • Feng Xie

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

  • Fu Li

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

Abstract

Taking inventories in reactor cores is critical for understanding their radioactive source terms and establishing the relationship between the activity concentration in the primary loop and the status of the reactor core’s fuel. However, there is a niche in which a simple but accurate relationship between reactor conditions and nuclide inventories can reliably predict the fission gas nuclide activities of the reactor core in the primary loop. In this study, a simple and efficient model called “Inventories of a Point Reactor for Fission Gas Nuclides” (IPRFGN) was proposed to calculate and interpret such inventories, in which a 10 MW high-temperature gas-cooled experimental reactor (HTR-10) was used as the test case. The present study findings were consistent with those of a general point–depletion burnup code such as the KORIGEN code. Here, the relative error was <1%. Based on the application of the IPRFGN model in HTR-10, the results indicate that the proposed IPRFGN model has provided the relationship between the inventories of fission gas nuclides in the core and the reactor conditions in all types of nuclear fission reactors. In the future, the IPRFGN model will be used for calculating fission gas nuclide inventories in various reactors.

Suggested Citation

  • Yu Wang & Jianzhu Cao & Feng Xie & Fu Li, 2023. "Inventories of Short-Lived Fission Gas Nuclides in Nuclear Reactors," Energies, MDPI, vol. 16(6), pages 1-19, March.
    • Handle: RePEc:gam:jeners:v:16:y:2023:i:6:p:2530-:d:1090418
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    References listed on IDEAS

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    1. Katarzyna Kiegiel & Irena Herdzik-Koniecko & Leon Fuks & Grażyna Zakrzewska-Kołtuniewicz, 2022. "Management of Radioactive Waste from HTGR Reactors including Spent TRISO Fuel—State of the Art," Energies, MDPI, vol. 15(3), pages 1-18, February.
    2. Menglei Cui & Yizhen Wang & Jiong Guo & Han Zhang & Fu Li, 2022. "Uncertainty Propagation of Fission Product Yields from Uranium and Plutonium in Pebble-Bed HTGR Burnup Calculation," Energies, MDPI, vol. 15(22), pages 1-12, November.
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