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Modeling and characterization of beryllium reflector elements under irradiation conditions

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주제분류원자력공학

초록

This study aims at modeling the beryllium reflector poisoning under neutron irradiation conditions and calculating the impact of beryllium poisoning on the core parameters of ETRR-2 research reactor. The CITVAP code was used to calculate the neutron flux and parameters of ETRR-2 core with beryllium reflector elements. The neutron flux in each reflector element was calculated to solve the modeling equations for the atomic densities of lithium-6 (6Li), tritium-3 (3H), and helium-3 (3He) using the BERYL program. The results are discussed based on CITVAP calculations of the core excess reactivity and cycle length Full Power Days (FPD). Possible solutions to minimize the degradation due to beryllium poisoning are also discussed and compared based on calculations.

Abstract

This study aims at modeling the beryllium reflector poisoning under neutron irradiation conditions and calculating the impact of beryllium poisoning on the core parameters of ETRR-2 research reactor. The CITVAP code was used to calculate the neutron flux and parameters of ETRR-2 core with beryllium reflector elements. The neutron flux in each reflector element was calculated to solve the modeling equations for the atomic densities of lithium-6 (6Li), tritium-3 (3H), and helium-3 (3He) using the BERYL program. The results are discussed based on CITVAP calculations of the core excess reactivity and cycle length Full Power Days (FPD). Possible solutions to minimize the degradation due to beryllium poisoning are also discussed and compared based on calculations.

참고문헌 (17)

  1. Ageing Management for Research Reactors, "IAEA", International Atomic Energy Agency (IAEA), ~, pp.Specific Safety Guide No. SSG-10 (2010)
  2. V. V. Kalygin, "Effect of 3He and 6Li accumulation in beryllium blocks on the neutron-physical characteristics of the MIR reactor", Atom. Energy, 104, pp.114~119 (2008)
  3. X. -L. Zou, "Analysis of beryllium poisoning effect on liquid metal reactor with U–Be alloy fuel", Nucl. Sci. Tech, 30(35), pp.7~ (2019)
  4. K. J. Andrzejewski, "Computations of fuel management in MARIA reactor with highly poisoned beryllium matrix", Nukleonika, 53, pp.173~179 (2008)
  5. David Chandler, "Transmutations in HFIR’s beryllium reflector and their impact on reactor operation and reflector disposal", Nucl. Technol, 177, pp.395~412 (2012)
  6. A. L. Izhutov, "SM Reactor Core Modernization Program", RRFM2017 Proceeding (2017)
  7. E. Villarino, "INVAP neutronic calculation line", Mec´anica Computacional, 33, pp.3217~3226 (2014)
  8. He-3 and Li-6 poisoning of the MARIA reactor beryllium matrix, "T. Kulikowska", Institute of Atomic Energy, ~, pp.Report IAE-40 (1999), A
  9. K.J. Andrzejewski, "Isotopic transmutations in irradiated beryllium and their implications on MARIA reactor operation", Nucl. Technol. Fusion, pp.72~82 (2004)
  10. Research Reactor Benchmarking Data Base, Facility Specification and Experimental Data, "IAEA", International Atomic Energy Agency (IAEA), ~, pp.Technical Reports Series No. 480 (2016)
  11. Elhefnawy, "Modeling and Characterization of Beryllium Reflector Elements under Irradiation Conditions", Master, pp.2019
  12. D. Amaya, "Improving the Cooling Conditions of the Irradiation Grid of a 22 MW Multipurpose Research Reactor", 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) (2005)
  13. F. Puig, "Neutron fluence effects on SLOWPOKE-2 beryllium reflector composition and reactivity", Nucl. Eng. Des, 305, pp.451~460 (2016)
  14. M. Aziz, "The effect of beryllium interaction with fast neutrons on the reactivity of ETRR-2 research reactor", Seventh Conference of Nuclear Sciences & Applications (2000)
  15. Benchmarking against Experimental Data of Neutronics and Thermohydraulic Computational Methods and Tools for Operation and Safety Analysis of Research Reactors, "IAEA", International Atomic Energy Agency (IAEA), ~, pp.IAEA-TECDOC-1879 (2019)
  16. L.E. Moloko, "Impact of Beryllium Reflector Ageing on SAFARI-1Reactor Core Parameters", Master, pp.2011
  17. G. R. Longhurst, "Managing beryllium in nuclear facility applications", Nucl. Technol, 176(3), pp.430~441 (2011)

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