title: ÐÑÐ¸Ð¼ÐµÐ½ÐµÐ½Ð¸Ðµ Ð´Ð²ÑÑ ÑÐ°Ð·Ð½ÑÑ ÑÐµÑÐ¼Ð¾ÑÐ¸ÑÐ¾Ð½Ð¾Ð² Ð² Ð¿ÑÐ¾ÑÐµÑÑÐµ Ð¾Ñ Ð»Ð°Ð¶Ð´ÐµÐ½Ð¸Ñ ÑÐ´ÐµÑÐ½Ð¾Ð³Ð¾ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° Ð² Ð±Ð°ÑÑÐµÐ¹Ð½Ðµ Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸ÑÑÐ°
titleType: Subtitle
title: The usage of two-phase closed thermosyphons in the process of nuclear fuel cooling in the spent fuel pool
Creators: name: ÐÐ¾ÑÐ±ÑÐ½Ð¾Ð², ÐÐ»ÐµÐºÑÐ°Ð½Ð´Ñ
Publisher: name: Ð¡Ð°Ð½ÐºÑ-ÐÐµÑÐµÑÐ±ÑÑÐ³ÑÐºÐ¸Ð¹ Ð¿Ð¾Ð»Ð¸ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ½Ð¸Ð²ÐµÑÑÐ¸ÑÐµÑ ÐÐµÑÑÐ° ÐÐµÐ»Ð¸ÐºÐ¾Ð³Ð¾
Year: 2023
Subjects: Ð¯Ð´ÐµÑÐ½Ð¾Ðµ Ð³Ð¾ÑÑÑÐµÐµ
Ð±Ð°ÑÑÐµÐ¹Ð½ Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸
Ð´Ð²ÑÑ ÑÐ°Ð·Ð½ÑÐ¹ ÑÐµÑÐ¼Ð¾ÑÐ¸ÑÐ¾Ð½
ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÑÑÑÐ°Ñ ÑÐ±Ð¾ÑÐºÐ°
Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð°Ñ Ð²ÑÐ³ÑÑÐ·ÐºÐ°
Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ
ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÐ°ÑÑÐµÑ
spent fuel pool
two-phase thermosyphon
fuel assembly
emergency unloading
neutron-physical calculation
heating calculations

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description: This work is devoted to assessing the applicability of two-phase thermosyphons in order to increase the reliability of spent fuel pools (SFP) cooling systems. Tasks that were solved during the work: 1. Study of the SFPâs structure and requirements for storage of fuel assemblies. 2. Calculation of the temperature distribution of SFPâs cooling water, the inner and outer shell of fuel rods, the gas gap and the fuel tablet along the height of the fuel rod in the event of an emergency unloading of the reactor core into the SFP 3. Calculation of the effective neutron multiplication coefficient for fuel assemblies placed in the SFP. 4. Two-phase thermosyphons installation options in SFP. 5. Calculation of evaporator and condenser sections of two-phase thermosyphons for different installation options. 6. Analysis of the results obtained during the calculations. 7. Forming a conclusion on the applicability of passive residual heat removal (PRHR) systems based on two-phase closed thermosyphons placed in the SFP. Calculations were carried out under the condition of emergency unloading of fuel assemblies from the reactor core into the spent fuel pool. The fuel assembly with the highest residual heat generation was selected for the thermal calculation. The neutron-physical calculation was carried out by the homogenization method of the unit cell of a heterogeneous lattice, which overestimates the effective neutron multiplication coefficient. The effect of the boron content in the structural material of SFPâs fuel racks on the effective neutron multiplication coefficient was taken into account during neutron-physical calculation. During the thermal calculation of two-phase thermosyphons, dimensional restrictions on their installation in SFP and options for their installation were determined, calculations of the lengths of evaporator and condenser zones were carried out. As a result, the distributions of water temperature in the SFP, temperature of the inner and outer shells of fuel rods, the gas gap and the fuel tablet along the height of the fuel rod, the effective neutron multiplication coefficient and its dependence on the boron content in the structural material of the of SFPâs fuel racks. The number of two-phase thermosyphons in the SFP and the overall characteristics of the thermosyphons for two installation options were obtained, and an assessment of the applicability of PRHR based on two-phase thermosyphon in SFP has been carried out.