title: Ð Ð°ÑÑÐµÑÑ ÑÐµÑÐµÐ½Ð¸Ñ Ð¸ ÑÐµÐ¿Ð»Ð¾Ð¾Ð±Ð¼ÐµÐ½Ð° Ð² ÑÑÑ Ð¾Ð¼ Ñ ÑÐ°Ð½Ð¸Ð»Ð¸ÑÐµ Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð²ÑÐµÐ³Ð¾ ÑÐ´ÐµÑÐ½Ð¾Ð³Ð¾ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°
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: Computations of flow and heat transfer in a dry storage of spent nuclear fuel
Creators: name: ÐÐ¾ÑÐ°Ðº, ÐÑÐ¼Ð°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ÑÐ¾Ð¼Ð½ÑÐµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÑÐ°Ð½ÑÐ¸Ð¸
Ð¯Ð´ÐµÑÐ½Ð¾Ðµ Ð³Ð¾ÑÑÑÐµÐµ
Ð Ð°Ð´Ð¸Ð¾Ð°ÐºÑÐ¸Ð²Ð½ÑÐµ Ð¾ÑÑ Ð¾Ð´Ñ
ÐÐ¾Ð½ÑÐµÐ¹Ð½ÐµÑÑ
Ð±Ð¾ÑÐºÐ¸ Ð´Ð»Ñ ÑÑÑ Ð¾Ð³Ð¾ Ñ ÑÐ°Ð½ÐµÐ½Ð¸Ñ
Ñ ÑÐ°Ð½ÐµÐ½Ð¸Ðµ Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð½Ð½Ð¾Ð³Ð¾ ÑÐ´ÐµÑÐ½Ð¾Ð³Ð¾ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°
Ð±ÐµÑÐ¾Ð½Ð½ÑÐ¹ ÐºÐ¾ÑÐ¿ÑÑ Ð´Ð»Ñ Ñ ÑÐ°Ð½ÐµÐ½Ð¸Ñ Ñ Ð¼ÐµÑÐ°Ð»Ð»Ð¸ÑÐµÑÐºÐ¸Ð¼ ÐºÐ¾Ð½ÑÐµÐ¹Ð½ÐµÑÐ¾Ð¼
cfd-Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð±Ð¾ÑÐºÐ¸ Ð´Ð»Ñ ÑÑÑ Ð¾Ð³Ð¾ Ñ ÑÐ°Ð½ÐµÐ½Ð¸Ñ
ÑÐ´ÐµÑÐ½ÑÐ¹ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½ÑÐ¹ ÑÐ¸ÐºÐ»
dry storage casks
storage of spent nuclear fuel
concrete storage cask with metal canister
cfd simulation of a dry storage cask
nuclear fuel cycle

description: ÐÑÐ¾Ð¼Ð½ÑÐµ ÑÐ»ÐµÐºÑÑÐ¾ÑÑÐ°Ð½ÑÐ¸Ð¸ ÑÐ²Ð»ÑÑÑÑÑ Ð½ÐµÐ¾ÑÑÐµÐ¼Ð»ÐµÐ¼Ð¾Ð¹ ÑÐ°ÑÑÑÑ ÑÐ¾ÑÐ¾ÑÐ¾ ÑÐ±Ð°Ð»Ð°Ð½ÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð½Ð¾Ð¹ ÑÑÑÑÐºÑÑÑÑ Ð¿ÑÐ¾Ð¸Ð·Ð²Ð¾Ð´ÑÑÐ²Ð° ÑÐ»ÐµÐºÑÑÐ¾ÑÐ½ÐµÑÐ³Ð¸Ð¸, ÑÐµÐ¼ ÑÐ°Ð¼ÑÐ¼ ÑÐ¿Ð¾ÑÐ¾Ð±ÑÑÐ²ÑÑ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¾Ð¹ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸. ÐÐ´Ð½Ð°ÐºÐ¾ Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð½Ð½Ð¾Ðµ ÑÐ´ÐµÑÐ½Ð¾Ðµ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð¾ Ð´Ð¾Ð»Ð¶Ð½Ð¾ ÑÑÐ°Ð½Ð¸ÑÑÑÑ Ð² ÑÑÐ»Ð¾Ð²Ð¸ÑÑ, ÑÐ°Ð·ÑÐ°Ð±Ð¾ÑÐ°Ð½Ð½ÑÑ Ð² ÑÐ¾Ð¾ÑÐ²ÐµÑÑÑÐ²Ð¸Ð¸ Ñ Ð¿ÑÐ°Ð²Ð¸Ð»Ð°Ð¼Ð¸, Ð¿Ð¾ÑÐºÐ¾Ð»ÑÐºÑ Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð½Ð½Ð¾Ðµ ÑÐ´ÐµÑÐ½Ð¾Ðµ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð¾ Ð²ÑÐ´ÐµÐ»ÑÐµÑ ÑÐµÐ¿Ð»Ð¾ÑÑ ÑÐ°ÑÐ¿Ð°Ð´Ð°, ÐºÐ¾ÑÐ¾ÑÐ°Ñ Ð¼Ð¾Ð¶ÐµÑ Ð½Ð°ÑÑÑÐ¸ÑÑ ÑÐµÐ»Ð¾ÑÑÐ½Ð¾ÑÑÑ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ð³Ð¾ ÑÐ»ÐµÐ¼ÐµÐ½ÑÐ°, ÐµÑÐ»Ð¸ Ð½Ðµ Ð¿ÑÐ¸Ð½ÑÑÑ Ð¼ÐµÑÑ Ð¿ÑÐµÐ´Ð¾ÑÑÐ¾ÑÐ¾Ð¶Ð½Ð¾ÑÑÐ¸. Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ Ð±ÑÐ»Ð° ÑÐ¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½ "ÑÑÑÐ¾Ð¹" ÐºÐ¾Ð½ÑÐµÐ¹Ð½ÐµÑ Ð´Ð»Ñ ÑÑÐ°Ð½ÐµÐ½Ð¸Ñ, ÐºÐ¾ÑÐ¾ÑÑÐ¹ ÑÐ²Ð»ÑÐµÑÑÑ ÑÐ°ÑÐ¿ÑÐ¾ÑÑÑÐ°Ð½ÐµÐ½Ð½ÑÐ¼ ÑÐµÑÐµÐ½Ð¸ÐµÐ¼ Ð´Ð»Ñ ÑÑÐ°Ð½ÐµÐ½Ð¸Ñ Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð½Ð½Ð¾Ð³Ð¾ ÑÐ´ÐµÑÐ½Ð¾Ð³Ð¾ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°. ÐÐ° Ð¾ÑÐ½Ð¾Ð²Ðµ Ð´Ð°Ð½Ð½ÑÑ, Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ Ð² ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ Ð¾Ð±Ð·Ð¾ÑÐ° Ð»Ð¸ÑÐµÑÐ°ÑÑÑÑ, Ð±ÑÐ»Ð° ÑÐ¾Ð·Ð´Ð°Ð½Ð° ÑÑÐµÑÐ¼ÐµÑÐ½Ð°Ñ Ð¼Ð¾Ð´ÐµÐ»Ñ ÑÐ¾ ÑÑÑÑÐºÑÑÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð½Ð¾Ð¹ ÑÐµÑÐºÐ¾Ð¹. ÐÐ¾ÑÐ»Ðµ ÑÑÐ¾Ð³Ð¾ Ð´Ð»Ñ Ð²ÑÑÐ¸ÑÐ»Ð¸ÑÐµÐ»ÑÐ½Ð¾Ð³Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð±ÑÐ»Ð¸ ÑÐ´ÐµÐ»Ð°Ð½Ñ ÑÐ¿ÑÐ¾ÑÐ°ÑÑÐ¸Ðµ Ð´Ð¾Ð¿ÑÑÐµÐ½Ð¸Ñ, Ð½Ðµ ÑÐ½Ð¸Ð¶Ð°ÑÑÐ¸Ðµ ÑÐ¾ÑÐ½Ð¾ÑÑÑ Ð¼Ð¾Ð´ÐµÐ»Ð¸. ÐÐ°ÑÐµÐ¼ Ð±ÑÐ»Ð° ÑÐ¾Ð·Ð´Ð°Ð½Ð° Ð¼Ð°ÑÐµÐ¼Ð°ÑÐ¸ÑÐµÑÐºÐ°Ñ Ð±Ð°Ð·Ð° Ñ Ð³ÑÐ°Ð½Ð¸ÑÐ½ÑÐ¼Ð¸ ÑÑÐ»Ð¾Ð²Ð¸ÑÐ¼Ð¸ Ð´Ð»Ñ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ. ÐÑÐ½Ð¾Ð²Ð½Ð¾Ð¹ Ð°Ð½Ð°Ð»Ð¸Ð· Ð±ÑÐ» Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ Ansys Fluent Ð¿ÑÐ¸ ÑÑÐ»Ð¾Ð²Ð¸ÑÑ Ð¾ÐºÑÑÐ¶Ð°ÑÑÐµÐ¹ ÑÑÐµÐ´Ñ 25 Â°C Ð¸ 1 Ð°ÑÐ¼. ÐÑÐµ ÑÐµÑÑÑÐµ ÑÐ¸Ð¼ÑÐ»ÑÑÐ¸Ð¸ Ð±ÑÐ»Ð¸ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ñ Ð´Ð»Ñ Ð¸Ð·ÑÑÐµÐ½Ð¸Ñ Ð²Ð»Ð¸ÑÐ½Ð¸Ñ Ð¼Ð¾Ð´ÐµÐ»Ð¸ ÑÑÑÐ±ÑÐ»ÐµÐ½ÑÐ½Ð¾ÑÑÐ¸, Ð±Ð¾Ð»ÐµÐµ ÑÐ¾Ð½ÐºÐ¾Ð¹ ÑÐµÑÐºÐ¸ Ð¸ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ Ð¾ÐºÑÑÐ¶Ð°ÑÑÐµÐ¹ ÑÑÐµÐ´Ñ. ÐÐ°ÐºÑÐ¸Ð¼Ð°Ð»ÑÐ½Ð°Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÐ° 358,67 K Ð½Ð°Ð±Ð»ÑÐ´Ð°Ð»Ð°ÑÑ Ð´Ð»Ñ Ð±Ð°Ð·Ð¾Ð²Ð¾Ð³Ð¾ Ð²Ð°ÑÐ¸Ð°Ð½ÑÐ°, Ð¸ Ð±Ð¾Ð»ÑÑÐ°Ñ ÑÐ°ÑÑÑ ÑÐµÐ¿Ð»Ð° ÑÐ°ÑÐ¿Ð°Ð´Ð° Ð±ÑÐ»Ð° Ð¾ÑÐ²ÐµÐ´ÐµÐ½Ð° ÐºÐ¾Ð½Ð²ÐµÐºÑÐ¸ÐµÐ¹. ÐÑÐ¾Ð¼Ðµ ÑÐ¾Ð³Ð¾, Ð±ÑÐ»Ð¾ Ð·Ð°Ð¼ÐµÑÐµÐ½Ð¾, ÑÑÐ¾ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÑ Ð² Ð¾ÑÐ½Ð¾Ð²Ð½Ð¾Ð¼ Ð½Ðµ Ð·Ð°Ð²Ð¸ÑÑÑ Ð¾Ñ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·ÑÐµÐ¼Ð¾Ð¹ Ð¼Ð¾Ð´ÐµÐ»Ð¸ ÑÑÑÐ±ÑÐ»ÐµÐ½ÑÐ½Ð¾ÑÑÐ¸ Ð¸Ð»Ð¸ Ð±Ð¾Ð»ÐµÐµ ÑÐ¾Ð½ÐºÐ¾Ð¹ ÑÐµÑÐºÐ¸, Ð½Ð¾ Ð½Ð° Ð½Ð¸Ñ ÑÑÑÐµÑÑÐ²ÐµÐ½Ð½Ð¾ Ð²Ð»Ð¸ÑÐµÑ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÐ° Ð¾ÐºÑÑÐ¶Ð°ÑÑÐµÐ³Ð¾ Ð²Ð¾Ð·Ð´ÑÑÐ°.
description: Nuclear power plants form an inseparable part of well-balanced electricity generationmix, thereby contributing to energy security. However, spent nuclear fuel shall bestored under conditions designed in accordance with regulations, as spent nuclear fuelemits decay heat, which may damage the integrity of fuel element, if precautions arenot taken. In this work, a dry storage cask, which is a widespread solution for storage of spentnuclear fuel, has been modelled. Based on data obtained through literature review, a3-D model has been generated with structured meshing. After that, simplifyingassumptions, without compromising the accuracy of model, were made forcomputational modelling. Following that, mathematical basis with boundaryconditions for modelling has been set up. Main analysis was conducted through Ansys Fluent with ambient conditions of 25 Â°Cand 1 atm. Four more simulations were done to investigate the effect of turbulencemodel, finer meshing and ambient temperature variation. Maximum temperature of358.67 K has been observed for the base case, and most of the decay heat wasrejected by convection. Furthermore, it has been observed that results remain mostlyunaffected by turbulence model used or finer meshing, but they were significantlyinfluenced by ambient air temperature.