title: ÐÐ½Ð°Ð»Ð¸Ð· Ð¾ÑÐ²Ð¾Ð´Ð° ÑÐµÐ¿Ð»Ð° Ð¾Ñ ÐÐ¢ÐÐ¡ Ð² Ð±Ð°ÑÑÐµÐ¹Ð½Ðµ Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸ ÐÐ­Ð¡ Â«Ð¥Ð°Ð½ÐºÐ¸ÐºÐ¸Ð²Ð¸-1Â» Ð² ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ ÑÐµÐ¶Ð¸Ð¼Ð°Ñ ÑÐ°Ð±Ð¾ÑÑ
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð±Ð°ÐºÐ°Ð»Ð°Ð²ÑÐ°
titleType: Subtitle
title: Analysis of heat removal from spent nuclear fuel in the fuel pool of Hanhikivi-1 NPP in different modes
Creators: name: Ð¡Ð¸Ð¼Ð°ÐºÐ¾Ð², ÐÐ¸ÑÐ°Ð¸Ð»
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: 2022
Subjects: ÐÐÐ­Ð -1200
Ð±Ð°ÑÑÐµÐ¹Ð½ Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸
ÑÐ¸ÑÑÐµÐ¼Ð° Ð¾Ñ Ð»Ð°Ð¶Ð´ÐµÐ½Ð¸Ñ Ð±Ð°ÑÑÐµÐ¹Ð½Ð° Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸
Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð²ÑÐ°Ñ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÑÑÑÐ°Ñ ÑÐ±Ð¾ÑÐºÐ°
Ð¢ÐÐ­Ð
VVER-1200
in-containment fuel pool
in-containment fuel pool cooling system
spent fuel assemblies
fuel ROD

description: Ð Ð²ÑÐ¿ÑÑÐºÐ½Ð¾Ð¹ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ Ð¸Ð·Ð»Ð¾Ð¶ÐµÐ½Ð¾ Ð¾Ð¿Ð¸ÑÐ°Ð½Ð¸Ðµ ÑÐ°Ð±Ð¾ÑÑ ÑÐ¸ÑÑÐµÐ¼Ñ Ð¾ÑÐ»Ð°Ð¶Ð´ÐµÐ½Ð¸Ñ Ð±Ð°ÑÑÐµÐ¹Ð½Ð° Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸ Ð¸ ÑÐ¸ÑÑÐµÐ¼, ÑÐ²ÑÐ·Ð°Ð½Ð½ÑÑ Ñ Ð¿Ð¾Ð´Ð¿Ð¸ÑÐºÐ¾Ð¹ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ð³Ð¾ Ð±Ð°ÑÑÐµÐ¹Ð½Ð°. ÐÑÐ»Ð¸ ÑÐ°ÑÑÐ¼Ð¾ÑÑÐµÐ½Ñ ÑÐ°ÑÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑ Ð¿Ð¾ Ð²ÑÑÐ¾ÑÐµ ÑÐ²ÑÐ»Ð° Ð² Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð²ÑÐµÐ¹ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ð¹ ÑÐ±Ð¾ÑÐºÐµ Ñ Ð¼Ð°ÐºÑÐ¸Ð¼Ð°Ð»ÑÐ½ÑÐ¼ Ð¾ÑÑÐ°ÑÐ¾ÑÐ½ÑÐ¼ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÐµÐ½Ð¸ÐµÐ¼ Ð¿ÑÐ¸ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð²ÑÐ³ÑÑÐ·ÐºÐµ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ Ð² ÑÑÐ»Ð¾Ð²Ð¸ÑÑ Ð½Ð¾ÑÐ¼Ð°Ð»ÑÐ½Ð¾Ð¹ ÑÐºÑÐ¿Ð»ÑÐ°ÑÐ°ÑÐ¸Ð¸ Ð¸ Ð¿ÑÐ¸ Ð¾Ð±ÐµÑÑÐ¾ÑÐ¸Ð²Ð°Ð½Ð¸Ð¸ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° Ð¿ÑÐ¸ ÑÑÑÐ°Ð½Ð¾Ð²Ð¸Ð²ÑÐµÐ¹ÑÑ ÐµÑÑÐµÑÑÐ²ÐµÐ½Ð½Ð¾Ð¹ ÑÐ¸ÑÐºÑÐ»ÑÑÐ¸Ð¸. Ð¢Ð°ÐºÐ¶Ðµ Ð±ÑÐ»Ð¸ ÑÐ°ÑÑÐ¼Ð¾ÑÑÐµÐ½Ñ Ð°Ð²Ð°ÑÐ¸Ð¸ Ñ Ð¿ÐµÑÐµÑÐ¾Ð´Ð¾Ð¼ Ð² ÑÐµÐ¶Ð¸Ð¼Ñ Ð·Ð°Ð¿ÑÐ¾ÐµÐºÑÐ½ÑÑ Ð°Ð²Ð°ÑÐ¸Ð¹ Ð¿ÑÐ¸ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ Ð¸ÑÑÐ¾Ð´Ð½ÑÑ ÑÐ¾Ð±ÑÑÐ¸ÑÑ, Ð° Ð¸Ð¼ÐµÐ½Ð½Ð¾ Ð¿ÑÐ¸ Ð¾Ð±ÐµÑÑÐ¾ÑÐ¸Ð²Ð°Ð½Ð¸Ð¸ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° Ð¸ Ð¿ÑÐ¸ ÑÐµÑÐ¸ Ð²Ð¾Ð´Ñ ÑÐµÑÐµÐ· ÑÑÑÐ±Ð¾Ð¿ÑÐ¾Ð²Ð¾Ð´ ÑÐ¸ÑÑÐµÐ¼Ñ Ð¾ÑÐ»Ð°Ð¶Ð´ÐµÐ½Ð¸Ñ Ð±Ð°ÑÑÐµÐ¹Ð½Ð° Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸ Ð¸ ÑÐµÑÐµÐ· Ð¾Ð±Ð»Ð¸ÑÐ¾Ð²ÐºÑ Ð±Ð°ÑÑÐµÐ¹Ð½Ð°. ÐÐ»Ñ Ð²ÑÐµÑ ÑÐ»ÑÑÐ°ÐµÐ² Ð±ÑÐ»Ð¸ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ñ Ð¿ÑÐ¾Ð¼ÐµÐ¶ÑÑÐºÐ¸ Ð²ÑÐµÐ¼ÐµÐ½Ð¸, Ð·Ð° ÐºÐ¾ÑÐ¾ÑÑÐµ Ð²Ð¾Ð´Ð° Ð·Ð°ÐºÐ¸Ð¿Ð¸Ñ, Ð¾Ð¿ÑÑÑÐ¸ÑÑÑ Ð´Ð¾ Ð¿ÐµÑÐµÐ³Ð¾ÑÐ¾Ð´ÐºÐ¸ Ð±Ð°ÑÑÐµÐ¹Ð½Ð° Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸ (Ð²ÑÐ»ÐµÐ´ÑÑÐ²Ð¸Ðµ ÑÐµÑÐ¸ Ð¸/Ð¸Ð»Ð¸ Ð²ÑÐ¿Ð°ÑÐ¸Ð²Ð°Ð½Ð¸Ñ) Ð¸ Ð²ÑÐºÐ¸Ð¿Ð¸Ñ Ð´Ð¾ Ð´Ð¾ÑÑÐ¸Ð¶ÐµÐ½Ð¸Ñ ÐµÑ Ð½Ð¸Ð·Ð° ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ð¹ ÑÐ°ÑÑÐ¸ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½ÑÑ ÐºÐ°ÑÑÐµÑ. ÐÐ¾ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ°Ð¼ ÑÐ°ÑÑÐµÑÐ¾Ð² Ð±ÑÐ»Ð¸ ÑÐ´ÐµÐ»Ð°Ð½Ñ Ð²ÑÐ²Ð¾Ð´Ñ, ÑÐºÐ¾Ð»ÑÐºÐ¾ Ð²ÑÐµÐ¼ÐµÐ½Ð¸ Ð±ÑÐ´ÐµÑ Ñ Ð¿ÐµÑÑÐ¾Ð½Ð°Ð»Ð° ÐÐ­Ð¡ Ð´Ð»Ñ Ð¿ÑÐµÐ´Ð¾ÑÐ²ÑÐ°ÑÐµÐ½Ð¸Ñ ÑÑÐºÐ°Ð»Ð°ÑÐ¸Ð¸ Ð°Ð²Ð°ÑÐ¸Ð¸. Ð¢Ð°ÐºÐ¶Ðµ Ð±ÑÐ»Ð¸ Ð¿Ð¾ÑÑÑÐ¾ÐµÐ½Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÐ½ÑÐµ ÑÐ°ÑÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ñ Ð¿Ð¾ Ð²ÑÑÐ¾ÑÐµ ÑÐ²ÑÐ»Ð° ÐºÐ°ÑÑÐµÑÑ Ñ Ð¼Ð°ÐºÑÐ¸Ð¼Ð°Ð»ÑÐ½ÑÐ¼ Ð¾ÑÑÐ°ÑÐ¾ÑÐ½ÑÐ¼ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÐµÐ½Ð¸ÐµÐ¼ Ð¿ÑÐ¸ ÐºÐ¸Ð¿ÐµÐ½Ð¸Ð¸ Ð²Ð¾Ð´Ñ Ð² Ð±Ð°ÑÑÐµÐ¹Ð½Ðµ Ð²ÑÐ´ÐµÑÐ¶ÐºÐ¸ Ð¸ Ð¿ÑÐ¸ Ð¿Ð¾Ð»Ð½Ð¾Ð¼ Ð¾Ð³Ð¾Ð»ÐµÐ½Ð¸Ð¸ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ð¹ ÑÐ°ÑÑÐ¸ ÐºÐ°ÑÑÐµÑÑ.
description: In the final qualifying work, a description of the operation of the in-containment fuel pool cooling system and description of the operation of the systems associated with the recharge of the fuel pool are presented. The temperature distributions over the height of the fuel rod in the spent fuel assembly with the maximum residual heat release during complete core unloading in normal operation and during de-energization of the power plant with established natural circulation were considered. Accidents with transition to the modes of beyond-design accidents at various initial events were also considered, namely, when the power plant is de-energized and when water flows through the pipeline of the cooling system of the holding pool and through the lining of the pool. For all cases, time intervals were determined for which the water will boil, descend to the partition of the fuel pool (due to leakage and /or evaporation) and boil off until it reaches the bottom of the fuel part of the fuel cartridges. Based on the results of the calculations, conclusions were made as to how much time the NPP personnel would have to prevent the escalation of the accident. Temperature distributions were constructed along the height of the fuel element of the cassette with the maximum residual heat release when water boils in the holding pool and when the fuel part of the cassette is completely exposed.