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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: Neutron radiation shielding calculation for the unique scientific facility âSpherical tokamak Globus-Mâ
Creators: name: ÐÐ°Ð·Ð°ÑÐµÐ², 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: 2024
Subjects: Ð£ÐÐ£ Â«Ð¡ÑÐµÑÐ¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ¾ÐºÐ°Ð¼Ð°Ðº ÐÐ»Ð¾Ð±ÑÑ-ÐÂ»
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unique scientific facility "Spherical tokamak Globus-M"
ionizing radiation
neutron radiation
neutron radiation of fusion facility
ionizing radiation shielding
neutron radiation shielding
neutron flux attenuation in matter
removal cross-section method

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° Ð¾ÑÐµÐ½ÐºÐµ Ð¼Ð¾ÑÐ½Ð¾ÑÑÐ¸ ÑÐºÐ²Ð¸Ð²Ð°Ð»ÐµÐ½ÑÐ½Ð¾Ð¹ Ð´Ð¾Ð·Ñ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾Ð³Ð¾ Ð¸Ð·Ð»ÑÑÐµÐ½Ð¸Ñ Ð² Ð¿ÑÐ»ÑÑÐ¾Ð²Ð¾Ð¹ Ð£ÐÐ£ Â«Ð¡ÑÐµÑÐ¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ¾ÐºÐ°Ð¼Ð°Ðº ÐÐ»Ð¾Ð±ÑÑ-ÐÂ», Ð° ÑÐ°ÐºÐ¶Ðµ ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð¸ ÑÐµÐ»ÐµÑÐ¾Ð¾Ð±ÑÐ°Ð·Ð½Ð¾ÑÑÐ¸ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ Ð²Ð°ÑÐ¸Ð°Ð½ÑÐ¾Ð² Ð±Ð¸Ð¾Ð»Ð¾Ð³Ð¸ÑÐµ-ÑÐºÐ¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ, Ð¿ÑÐµÐ´Ð½Ð°Ð·Ð½Ð°ÑÐµÐ½Ð½Ð¾Ð¹ Ð´Ð»Ñ ÑÐ½Ð¸Ð¶ÐµÐ½Ð¸Ñ Ð¿Ð¾Ð»ÑÑÐ°ÐµÐ¼Ð¾Ð¹ Ð¿ÐµÑÑÐ¾Ð½Ð°Ð»Ð¾Ð¼ ÑÑÐµÐ´Ð½Ðµ-Ð³Ð¾Ð´Ð¾Ð²Ð¾Ð¹ ÑÐºÐ²Ð¸Ð²Ð°Ð»ÐµÐ½ÑÐ½Ð¾Ð¹ Ð´Ð¾Ð·Ñ. Ð Ð°Ð±Ð¾ÑÐ° Ð¿ÑÐ¾Ð²Ð¾Ð´Ð¸Ð»Ð°ÑÑ Ð½Ð° Ð±Ð°Ð·Ðµ Ð¤ÐÐÐ£ Ð¤Ð¢Ð Ð¸Ð¼. Ð.Ð¤. ÐÐ¾ÑÑÐµ Ð ÐÐ, Ð³Ð´Ðµ Ð±ÑÐ»Ð° Ð¸Ð·Ð¼ÐµÑÐµÐ½Ð° Ð³ÐµÐ¾Ð¼ÐµÑÑÐ¸Ñ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½Ð¾Ð³Ð¾ Ð·Ð°Ð»Ð° Ð¸ Ð¿ÑÐ»ÑÑÐ¾Ð²Ð¾Ð¹, Ð° ÑÐ°ÐºÐ¶Ðµ Ð¿Ð¾Ð»ÑÑÐµÐ½Ñ Ð´Ð°Ð½Ð½ÑÐµ Ð¾ Ð¿Ð¾ÑÐ¾ÐºÐµ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð¾Ð² Ð¸Ð· ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸. ÐÐ° Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ð¸ ÑÑÐ¸Ñ Ð´Ð°Ð½Ð½ÑÑ Ð±ÑÐ»Ð¸ Ð²ÑÑÐ¸ÑÐ»ÐµÐ½Ñ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑ ÑÐ»ÑÐµÐ½ÑÐ° Ð¸ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑ ÑÐºÐ²Ð¸Ð²Ð°Ð»ÐµÐ½ÑÐ½Ð¾Ð¹ Ð´Ð¾Ð·Ñ Ð±ÑÑÑÑÑÑ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð¾Ð² Ð² Ð¿ÑÐ»ÑÑÐ¾Ð²Ð¾Ð¹, Ð° ÑÐ°ÐºÐ¶Ðµ ÑÑÐµÐ´Ð½ÐµÐ³Ð¾Ð´Ð¾Ð²Ð°Ñ ÑÐºÐ²Ð¸Ð²Ð°Ð»ÐµÐ½ÑÐ½Ð°Ñ Ð´Ð¾Ð·Ð°, Ð¿Ð¾Ð»ÑÑÐ°Ðµ-Ð¼Ð°Ñ Ð¿ÐµÑÑÐ¾Ð½Ð°Ð»Ð¾Ð¼. ÐÐ»Ñ ÑÐ°ÑÑÑÑÐ° Ð¾ÑÐ»Ð°Ð±Ð»ÐµÐ½Ð¸Ñ Ð¿Ð¾ÑÐ¾ÐºÐ° Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð¾Ð² Ð½Ð° Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ð¸ Ð¿Ð¾Ð»Ð½Ð¾Ð³Ð¾ ÑÐµÑÐµÐ½Ð¸Ñ Ð²Ð·Ð°Ð¸Ð¼Ð¾Ð´ÐµÐ¹ÑÑÐ²Ð¸Ñ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð¾Ð² Ð¸ Ð´Ð¸ÑÑÐµÑÐµÐ½ÑÐ¸Ð°Ð»ÑÐ½Ð¾Ð³Ð¾ ÑÐµÑÐµÐ½Ð¸Ñ ÑÐ°ÑÑÐµÑÐ½Ð¸Ñ, Ð¿Ð¾Ð»Ñ-ÑÐµÐ½Ð½ÑÑ Ð¸Ð· Ð±Ð°Ð·Ñ Ð´Ð°Ð½Ð½ÑÑ ENDF/B-VII.1, Ð²ÑÑÐ¸ÑÐ»ÑÐ»Ð¸ÑÑ ÑÐµÑÐµÐ½Ð¸Ñ Ð²ÑÐ²ÐµÐ´ÐµÐ½Ð¸Ñ ÑÐ°Ð·-Ð»Ð¸ÑÐ½ÑÑ ÑÐ¸Ð¼Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐ»ÐµÐ¼ÐµÐ½ÑÐ¾Ð². ÐÑÐ»Ð¸ ÑÐ°ÑÑÐ¼Ð¾ÑÑÐµÐ½Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÐµ Ð²Ð°ÑÐ¸Ð°Ð½ÑÑ Ð·Ð°ÑÐ¸ÑÑ; Ð´Ð»Ñ Ð½Ð¸Ñ Ð±ÑÐ»Ð¸ Ð²ÑÑÐ¸ÑÐ»Ðµ-Ð½Ñ Ð¼Ð¾ÑÐ½Ð¾ÑÑÐ¸ ÑÐ»ÑÐµÐ½ÑÐ° Ð¸ ÑÐºÐ²Ð¸Ð²Ð°Ð»ÐµÐ½ÑÐ½Ð¾Ð¹ Ð´Ð¾Ð·Ñ Ð±ÑÑÑÑÑÑ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð¾Ð², Ð° ÑÐ°ÐºÐ¶Ðµ ÑÑÐµÐ´Ð½ÐµÐ³Ð¾Ð´Ð¾Ð²Ð°Ñ ÑÐºÐ²Ð¸Ð²Ð°Ð»ÐµÐ½ÑÐ½Ð°Ñ Ð´Ð¾Ð·Ð°. ÐÐ° Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ð¸ Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ¾Ð² Ð±Ñ-Ð»Ð¸ ÑÐ´ÐµÐ»Ð°Ð½Ñ Ð²ÑÐ²Ð¾Ð´Ñ Ð¾Ð± Ð¸Ñ ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð¸ ÑÐµÐ»ÐµÑÐ¾Ð¾Ð±ÑÐ°Ð·Ð½Ð¾ÑÑÐ¸.
description: The given work is devoted to estimate equivalent dose rate of neutron radia-tion in control room of the unique scientific facility âSpherical tokamak Globus-Mâ and to estimate efficiency and feasibility of different options for neutron shielding, which is designed to decrease the received by personnel average annual equivalent dose. The work has been done on the base of the Ioffe Physical-Technical Institute of the Russian Academy of Sciences, where the geometrical parameters of facility and control room have been measured and data for neutron flux has been received. Basing on this data the fluence rate, equivalent dose rate and received by personnel average annual equivalent dose have been calculated. To calculate the neutron flux attenuation in matter removal cross-sections of different chemical compounds have been calculated, basing on total interaction cross-sections and cross-section angular distributions, which have been received from ENDF/B-VII.1 database. Different options for neutron shielding have been considered. The fluence rate, equivalent dose rate and received by personnel average annual equivalent dose have been calculated for these shieldings. Basing on obtained results conclusions about shielding efficiency and feasibility have been done.