title: ÐÐ½Ð°Ð»Ð¸Ð· ÑÐµÐ¿Ð»Ð¾Ð¼ÐµÑ Ð°Ð½Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð¿Ð¾Ð²ÐµÐ´ÐµÐ½Ð¸Ñ ÑÐ²ÑÐ»Ð¾Ð² Ñ Ð¾ÐºÑÐ¸Ð´Ð½ÑÐ¼ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð¾Ð¼ Ð´Ð»Ñ ÑÐ»ÑÑÐ°ÐµÐ² Ð³Ð»ÑÐ±Ð¾ÐºÐ¾Ð³Ð¾ Ð²ÑÐ³Ð¾ÑÐ°Ð½Ð¸Ñ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÐÐÐ­Ð -1000 Ð¿ÑÐ¸ ÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½ÑÑ ÑÐµÐ¶Ð¸Ð¼Ð°Ñ ÑÐ°Ð±Ð¾ÑÑ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ FRAPCON
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¼Ð°Ð³Ð¸ÑÑÑÐ°
titleType: Subtitle
title: Analysis of the steady-state thermal-mechanical behavior of oxide fuel rods for high burnup in VVER 1000 reactor using FRAPCON
Creators: name: ÐÐ³ÑÐ·ÑÐ°Ð½, ÐÐ°Ð¹Ðµ
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Ð½ÑÐµ ÑÐµÐ°ÐºÑÐ¾ÑÑ Ð²Ð¾Ð´Ð¾-Ð²Ð¾Ð´ÑÐ½ÑÐµ
Ð¯Ð´ÐµÑÐ½Ð¾Ðµ Ð³Ð¾ÑÑÑÐµÐµ

description: ÐÐ½Ð°Ð»Ð¸Ð· ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸Ðº ÑÐ´ÐµÑÐ½Ð¾Ð³Ð¾ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° ÑÐ²Ð»ÑÐµÑÑÑ Ð¾ÑÐ½Ð¾Ð²Ð¾Ð¿Ð¾Ð»Ð°Ð³Ð°ÑÑÐ¸Ð¼ Ð´Ð»Ñ Ð¸Ð·ÑÑÐµÐ½Ð¸Ñ ÑÐµÑÐ¼Ð¾Ð¼ÐµÑÐ°Ð½Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð¿Ð¾Ð²ÐµÐ´ÐµÐ½Ð¸Ñ Ð¾ÐºÑÐ¸Ð´Ð½ÑÑ ÑÐ²ÑÐ»Ð¾Ð². Ð¢Ð¾Ð¿Ð»Ð¸Ð²Ð½ÑÐ¹ ÑÑÐµÑÐ¶ÐµÐ½Ñ Ð¸ÑÐ¿ÑÑÑÐ²Ð°ÐµÑ ÑÐ¿ÑÑÐ³Ð¾-Ð¿Ð»Ð°ÑÑÐ¸ÑÐµÑÐºÑÑ Ð´ÐµÑÐ¾ÑÐ¼Ð°ÑÐ¸Ñ, ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ðµ ÑÐ°ÑÑÐ¸ÑÐµÐ½Ð¸Ðµ, ÑÐ°ÑÑÑÐµÑÐºÐ¸Ð²Ð°Ð½Ð¸Ðµ, ÑÐ°ÑÐ¿ÑÑÐ°Ð½Ð¸Ðµ Ð¿ÑÐ¸ Ð¾Ð±Ð»ÑÑÐµÐ½Ð¸Ð¸ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°, ÑÐ¿Ð»Ð¾ÑÐ½ÐµÐ½Ð¸Ðµ, Ð¼ÐµÑÐ°Ð½Ð¸ÑÐµÑÐºÐ¾Ðµ Ð²Ð·Ð°Ð¸Ð¼Ð¾Ð´ÐµÐ¹ÑÑÐ²Ð¸Ðµ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° Ñ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¾Ð¹, Ð¿Ð¾Ð»Ð·ÑÑÐµÑÑÑ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸ Ð¸ ÑÐ°Ðº Ð´Ð°Ð»ÐµÐµ. Ð­ÑÐ¸ ÑÐ²Ð»ÐµÐ½Ð¸Ñ Ð²Ð»Ð¸ÑÑÑ Ð½Ð° ÑÐ°Ð·Ð¼ÐµÑ, ÑÐ¾ÑÐ¼Ñ Ð¸ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸ Ð¼Ð°ÑÐµÑÐ¸Ð°Ð»Ð° ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° Ð¸ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸ Ð¿Ð¾Ð´ Ð²Ð¾Ð·Ð´ÐµÐ¹ÑÑÐ²Ð¸ÐµÐ¼ ÑÐ°ÐºÐ¸Ñ ÑÐ°ÐºÑÐ¾ÑÐ¾Ð², ÐºÐ°Ðº Ð¼ÐµÑÐ°Ð½Ð¸ÑÐµÑÐºÐ¸Ðµ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ, Ð²ÑÑÐ¾ÐºÐ°Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÐ°, Ð²Ð·Ð°Ð¸Ð¼Ð¾Ð´ÐµÐ¹ÑÑÐ²Ð¸Ðµ Ñ Ð¿Ð¾ÑÐ¾ÐºÐ¾Ð¼ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð¾Ð² Ð¸ ÑÐ¸Ð¼Ð¸ÑÐµÑÐºÐ°Ñ ÑÑÐµÐ´Ð° Ð²Ð¾ Ð²ÑÐµÐ¼Ñ Ð¾Ð±Ð»ÑÑÐµÐ½Ð¸Ñ. Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ ÑÐ°ÑÑÐ¼Ð°ÑÑÐ¸Ð²Ð°ÐµÑÑÑ Ð°Ð½Ð°Ð»Ð¸Ð· Ð¿Ð¾Ð²ÐµÐ´ÐµÐ½Ð¸Ñ ÑÐ²ÑÐ»Ð° ÐÐÐ­Ð -1000. ÐÐ¾Ð´ FRAPCON-4.0 Ð¸ÑÐ¿Ð¾Ð»ÑÐ·ÑÐµÑÑÑ Ð´Ð»Ñ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑÑÑÐ°Ð½Ð¾Ð²Ð¸Ð²ÑÐµÐ³Ð¾ÑÑ ÑÐµÐ¶Ð¸Ð¼Ð° ÑÐ°Ð±Ð¾ÑÑ ÑÐ²ÑÐ»Ð° Ð¿ÑÐ¸ Ð²ÑÑÐ¾ÐºÐ¾Ð¼ Ð²ÑÐ³Ð¾ÑÐ°Ð½Ð¸Ð¸. ÐÐ¾Ð´ ÑÐ°ÑÑÑÐ¸ÑÑÐ²Ð°ÐµÑ Ð·Ð½Ð°ÑÐ¸Ð¼ÑÐµ Ð¿ÐµÑÐµÐ¼ÐµÐ½Ð½ÑÐµ ÑÐ²ÑÐ»Ð°, Ð²ÐºÐ»ÑÑÐ°Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° Ð¸ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸, Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ðµ-Ð´ÐµÑÐ¾ÑÐ¼Ð°ÑÐ¸Ñ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸, Ð¿ÐµÑÐµÐ¼ÐµÑÐµÐ½Ð¸Ðµ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°, Ð¾ÐºÐ¸ÑÐ»ÐµÐ½Ð¸Ðµ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸, Ð·Ð°ÑÐ²Ð°Ñ Ð²Ð¾Ð´Ð¾ÑÐ¾Ð´Ð°, ÑÐ°ÑÐ¿ÑÑÐ°Ð½Ð¸Ðµ Ð¸ ÑÐ¿Ð»Ð¾ÑÐ½ÐµÐ½Ð¸Ðµ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°, Ð²ÑÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ Ð³Ð°Ð·Ð¾Ð² Ð´ÐµÐ»ÐµÐ½Ð¸Ñ, ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½Ñ ÑÐµÐ¿Ð»Ð¾Ð¿ÐµÑÐµÐ´Ð°ÑÐ¸ Ð·Ð°Ð·Ð¾ÑÐ° Ð¸ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ðµ Ð³Ð°Ð·Ð° Ð²Ð½ÑÑÑÐ¸ ÑÑÐµÑÐ¶Ð½Ñ. ÐÐ°Ð¼ÐµÑÐµÐ½Ð¾, ÑÑÐ¾ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ðµ Ð³Ð°Ð·Ð° Ð½ÐµÑÐºÐ»Ð¾Ð½Ð½Ð¾ ÑÐ°ÑÑÐµÑ Ð¸Ð·-Ð·Ð° Ð½ÐµÐ¿ÑÐµÑÑÐ²Ð½Ð¾Ð³Ð¾ Ð²ÑÐ´ÐµÐ»ÐµÐ½Ð¸Ñ Ð´ÐµÐ»ÑÑÐµÐ³Ð¾ÑÑ Ð³Ð°Ð·Ð° Ð¸ ÑÐ¼ÐµÐ½ÑÑÐµÐ½Ð¸Ñ ÑÐ¾Ð»ÑÐ¸Ð½Ñ Ð·Ð°Ð·Ð¾ÑÐ°. ÐÐ°Ð²Ð»ÐµÐ½Ð¸Ðµ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ Ð¸ Ð²Ð½ÑÑÑÐµÐ½Ð½ÐµÐµ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ðµ ÑÐ²Ð»ÑÑÑÑÑ Ð¾ÑÐ½Ð¾Ð²Ð½ÑÐ¼Ð¸ Ð¿ÑÐ¸ÑÐ¸Ð½Ð°Ð¼Ð¸ Ð´ÐµÑÐ¾ÑÐ¼Ð°ÑÐ¸Ð¸ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸. ÐÐ¾ÐºÐ°Ð·Ð°Ð½Ð¾, ÑÑÐ¾ ÑÐ½Ð°ÑÐ°Ð»Ð° Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ðµ Ð² Ð¾Ð±ÑÑÑÐµ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸ Ð¾ÑÑÐ°ÐµÑÑÑ ÑÐ¶Ð¸Ð¼Ð°ÑÑÐ¸Ð¼, Ð° Ð·Ð°ÑÐµÐ¼ Ð²Ð¾Ð·Ð½Ð¸ÐºÐ°ÐµÑ ÑÐ°ÑÑÑÐ³Ð¸Ð²Ð°ÑÑÐµÐµ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ðµ Ð² Ð¾Ð±ÑÑÑÐµ, ÑÐ°Ðº ÐºÐ°Ðº Ð³ÑÐ°Ð½ÑÐ»Ñ Ð¾ÐºÐ°Ð·ÑÐ²Ð°ÑÑ Ð²Ð½ÐµÑÐ½ÐµÐµ Ð²Ð¾Ð·Ð´ÐµÐ¹ÑÑÐ²Ð¸Ðµ Ð½Ð° Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÑ. Ð¢Ð°ÐºÐ¶Ðµ ÑÑÐ°Ð²Ð½Ð¸Ð²Ð°ÐµÑÑÑ ÑÐ°ÑÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ Ð¼ÐµÐ¶Ð´Ñ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð¾Ð¼, Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¾Ð¹ Ð¸ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»ÐµÐ¼.
description: Nuclear fuel performance analysis is fundamental to examine the thermal-mechanical behavior of oxide fuel rods. The fuel rod experiences elastic-plastic deformation, thermal expansion, cracking, fuel irradiation swelling, densification, fuel-cladding mechanical interaction, cladding creep and so on. These phenomena affect the size, form and material characteristics of fuel and cladding caused by factors such as mechanical stresses, high temperature, interaction with the neutron flux and chemical environment during irradiation. This study reviews the fuel rod behavior analysis of VVER-1000. FRAPCON-4.0 code is used to simulate the steady-state response of the fuel rod for high burnup. The code calculates the significant fuel rod variables, including fuel and cladding temperature, cladding stress-strain, fuel relocation, cladding oxidation, hydrogen pickup, fuel swelling and densification, fission gas release, gap heat transfer coefficient, and rod internal gas pressure. It is observed that the gas pressure steadily increases due to the continuous fission gas release and the gap thickness reduction. The coolant and internal pressure are the main reasons for cladding stress-strain. It is shown that, first, the cladding hoop stress stays compressive, and then experiences a tensile hoop stress as pellets impose an outward force onto cladding. Temperature distribution is also compared between fuel, cladding and coolant.