title: ÐÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð¾ÑÐ»Ð°Ð±Ð»ÐµÐ½Ð¸Ñ Ð³Ð°Ð¼Ð¼Ð°-Ð¸Ð·Ð»ÑÑÐµÐ½Ð¸Ñ ÑÑÐ³ÑÐ½Ð½ÑÐ¼ ÐºÐ¾Ð½ÑÐµÐ¹Ð½ÐµÑÐ¾Ð¼ Ð´Ð»Ñ Ð¾ÑÑÐ°Ð±Ð¾ÑÐ°Ð²ÑÐµÐ³Ð¾ Ð³ÑÐ°ÑÐ¸ÑÐ¾Ð²Ð¾Ð³Ð¾ Ð·Ð°Ð¼ÐµÐ´Ð»Ð¸ÑÐµÐ»Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÑÐ¸Ð¿Ð° Ð ÐÐÐ-1000
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: Investigation of the attenuation of gamma radiation by a cast-iron container for a spent graphite moderator of an RBMK-1000 typed reactor
Creators: name: Ð¯ÑÐ¼ÑÑÐ°Ð¼ÐµÐ´Ð¾Ð², Ð­Ð¼Ð¸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: Ð¾Ð±Ð»ÑÑÐµÐ½Ð½ÑÐ¹ ÑÐµÐ°ÐºÑÐ¾ÑÐ½ÑÐ¹ Ð³ÑÐ°ÑÐ¸Ñ
Ð²ÑÑÐ¾ÐºÐ¾Ð¿ÑÐ¾ÑÐ½ÑÐ¹ ÑÑÐ³ÑÐ½ Ñ ÑÐ°ÑÐ¾Ð²Ð¸Ð´Ð½ÑÐ¼ Ð³ÑÐ°ÑÐ¸ÑÐ¾Ð¼
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ÑÑÐ°Ð½ÑÐ¿Ð¾ÑÑÐ½ÑÐ¹ ÑÐ¿Ð°ÐºÐ¾Ð²Ð¾ÑÐ½ÑÐ¹ ÐºÐ¾Ð¼Ð¿Ð»ÐµÐºÑ
irradiated reactor graphite
spheroidal graphite high-strength cast iron
urabium0graphite reactor
RBMC
LAES
transport packing set

description: Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ ÑÐ°ÑÑÐ¼Ð¾ÑÑÐµÐ½ ÑÑÐ³ÑÐ½Ð½ÑÐ¹ ÑÑÐ°Ð½ÑÐ¿Ð¾ÑÑÐ½Ð¾-ÑÐ¿Ð°ÐºÐ¾Ð²Ð¾ÑÐ½ÑÐ¹ ÐºÐ¾Ð½ÑÐµÐ¹Ð½ÐµÑ ÑÐ¾Ð»ÑÐ¸Ð½Ð¾Ð¹ 80 Ð¼Ð¼ Ð´Ð»Ñ Ð¾Ð±Ð»ÑÑÑÐ½Ð½Ð¾Ð³Ð¾ Ð³ÑÐ°ÑÐ¸ÑÐ° Ð¸ Ð¿ÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÑÐ½ ÑÐ°ÑÑÑÑ Ð·Ð°ÑÐ¸ÑÐ½ÑÑ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸Ðº â ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ¾Ð² Ð¾ÑÐ»Ð°Ð±Ð»ÐµÐ½Ð¸Ñ, ÑÐ¸ÑÐ»Ð¾Ð²Ð¾Ð³Ð¾ Ð¸ Ð´Ð¾Ð·Ð¾Ð²Ð¾Ð³Ð¾ ÑÐ°ÐºÑÐ¾ÑÐ¾Ð² Ð½Ð°ÐºÐ¾Ð¿Ð»ÐµÐ½Ð¸Ñ. Ð ÑÐ¾Ð´Ðµ ÑÐ°Ð±Ð¾ÑÑ ÑÐµÑÐ°Ð»Ð¸ÑÑ ÑÐ»ÐµÐ´ÑÑÑÐ¸Ðµ Ð·Ð°Ð´Ð°ÑÐ¸: 1. ÐÑÐ¸Ð¼ÐµÐ½ÐµÐ½Ð¸Ðµ Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ð½Ð¾Ð³Ð¾ Ð¿Ð°ÐºÐµÑÐ° MCC-3D; 2. Ð§Ð¸ÑÐ»ÐµÐ½Ð½Ð¾Ðµ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð¸Ð¾Ð½Ð¸Ð·Ð¸ÑÑÑÑÐµÐ³Ð¾ Ð¸Ð·Ð»ÑÑÐµÐ½Ð¸Ñ; 3. ÐÑÐµÐ½ÐºÐ° ÑÐ°Ð´Ð¸Ð°ÑÐ¸Ð¾Ð½Ð½Ð¾Ð³Ð¾ ÑÐ°Ð·Ð¾Ð³ÑÐµÐ²Ð° Ð¢Ð£Ð. Ð¢Ð°ÐºÐ¶Ðµ Ð¿ÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½Ð¾ ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾Ðµ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ ÑÐµÐ¿Ð»Ð¾Ð¾ÑÐ²Ð¾Ð´Ð° Ð¾Ñ ÐºÐ¾Ð½ÑÐµÐ¹Ð½ÐµÑÐ° Ñ Ð¾Ð±ÑÐµÐ¼Ð½ÑÐ¼Ð¸ Ð¸ÑÑÐ¾ÑÐ½Ð¸ÐºÐ°Ð¼Ð¸ ÑÐµÐ¿Ð»Ð¾ÑÑ Ñ Ð¿ÑÐ¸Ð¼ÐµÐ½ÐµÐ½Ð¸ÐµÐ¼ Ð¿ÑÐ¸ÐºÐ»Ð°Ð´Ð½Ð¾Ð³Ð¾ ÐÐ Ansys. ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° ÑÐ²Ð»ÑÐµÑÑÑ Ð¾ÑÐ½Ð¾Ð²Ð¾Ð¹ Ð´Ð»Ñ Ð´Ð°Ð»ÑÐ½ÐµÐ¹ÑÐµÐ³Ð¾ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÐºÐ¾Ð½ÑÐµÐ¿ÑÐ° ÑÑÐ³ÑÐ½Ð½Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÐµÐ¹Ð½ÐµÑÐ°. Ð Ð¿ÐµÑÑÐ¿ÐµÐºÑÐ¸Ð²Ðµ Ð½ÐµÐ¾Ð±ÑÐ¾Ð´Ð¸Ð¼Ð¾ Ð¿ÑÐ¾Ð²ÐµÑÑÐ¸ Ð¿ÑÐ¾ÑÐ½Ð¾ÑÑÐ½Ð¾Ð¹, ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÐ°ÑÑÑÑÑ, Ð¿ÑÐ¾Ð°Ð½Ð°Ð»Ð¸Ð·Ð¸ÑÐ¾Ð²Ð°ÑÑ ÑÐ¾ÑÑÐ°Ð² Ð³ÑÐ°ÑÐ¸ÑÐ° Ð½Ð° ÐÐÐ­Ð¡ Ð¸ Ð¿Ð¾ÑÑÐ¸ÑÐ°ÑÑ Ð·Ð°ÑÐ¸ÑÐ½ÑÐµ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸ Ð´Ð»Ñ ÐºÐ¾Ð½ÐºÑÐµÑÐ½Ð¾Ð³Ð¾ ÑÐ»ÑÑÐ°Ñ. ÐÐ¾Ð»ÑÑÐµÐ½Ð½ÑÐµ ÑÐ°Ð±Ð»Ð¸ÑÑ ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ¾Ð² Ð¾ÑÐ»Ð°Ð±Ð»ÐµÐ½Ð¸Ñ Ð¸ Ð¿ÑÐµÐ´ÐµÐ»ÑÐ½Ð¾ Ð´Ð¾Ð¿ÑÑÑÐ¸Ð¼ÑÑ Ð´Ð¾Ð· Ð¼Ð¾Ð³ÑÑ Ð¿Ð¾ÑÐ»ÑÐ¶Ð¸ÑÑ Ð±Ð°Ð·Ð¾Ð¹ Ð´Ð»Ñ Ð¿Ð¾ÑÐ»ÐµÐ´ÑÑÑÐ¸Ñ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ð¹.
description: In this work a cast-iron transport-packaging container 80 mm thick for irradiated graphite is considered and protective characteristics - attenuation coefficients, numerical and dose accumulation factors - are calculated. In the course of the work the following tasks were solved: 1. Application of MCC-3D software package; 2. Numerical modeling of ionizing radiation; 3. Estimation of radiation heating of a transport-packing container. Numerical modeling of heat removal from a container with volumetric heat sources was also performed using the Ansys application software. This work is the basis for further designing the concept of a cast-iron container. In the future, it is necessary to carry our strength and thermal calculations, analyze the composition of graphite at Leningrad NPP and calculate the protective characteristics for a particular case. The resulting tables of attenuation coefficient and maximum allowable doses can serve as a basis for subsequent studies.