title: ÐÐ±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ðµ ÐºÑÐ¸ÑÐµÑÐ¸ÐµÐ² Ð²ÑÐ¿Ð¸ÑÐºÐ¸ Ð±Ð¾Ð»ÑÐ½ÑÑ Ð¿Ð¾ÑÐ»Ðµ ÑÐ°Ð´Ð¸Ð¾Ð½ÑÐºÐ»Ð¸Ð´Ð½Ð¾Ð¹ ÑÐµÑÐ°Ð¿Ð¸Ð¸ Sm-153, Sr-89, Lu-177, I-131
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: Justification of discharge criteria for patients after radionuclide therapy Sm-153, Sr-89, Lu-177, I-131
Creators: name: Ð¦Ð²Ð¸ÑÐ³ÑÐ½, ÐÑÐµÐ½Ð¸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: ÑÐ°Ð´Ð¸Ð¾Ð½ÑÐºÐ»Ð¸Ð´Ð½Ð°Ñ ÑÐµÑÐ°Ð¿Ð¸Ñ
Ð»ÑÑÐµÑÐ¸Ð¹-177
ÑÐ°Ð¼Ð°ÑÐ¸Ð¹-153
ÑÑÑÐ¾Ð½ÑÐ¸Ð¹-89
Ð¹Ð¾Ð´-131
ÑÐ°Ð´Ð¸Ð¾Ð»Ð¾Ð³Ð¸ÑÐµÑÐºÐ¸Ðµ ÐºÑÐ¸ÑÐµÑÐ¸Ð¸ Ð²ÑÐ¿Ð¸ÑÐºÐ¸
ÑÐ°Ð´Ð¸Ð°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÑ
radionuclide therapy
lutetium-177
samarium-153
strontium-89
iodine-131
radiological discharge criteria
radiation safety

description: Ð¦ÐµÐ»ÑÑ Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÑ ÑÐ²Ð»ÑÐµÑÑÑ Ð½Ð°ÑÑÐ½Ð¾Ðµ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ðµ ÑÐ°Ð´Ð¸Ð¾Ð»Ð¾Ð³Ð¸ÑÐµÑÐºÐ¸Ñ ÐºÑÐ¸ÑÐµÑÐ¸ÐµÐ² Ð²ÑÐ¿Ð¸ÑÐºÐ¸ Ñ ÑÑÐµÑÐ¾Ð¼ Ð¾Ð±Ð»ÑÑÐµÐ½Ð¸Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ ÐºÐ°ÑÐµÐ³Ð¾ÑÐ¸Ð¹ Ð»Ð¸Ñ, ÐºÐ¾Ð½ÑÐ°ÐºÑÐ¸ÑÑÑÑÐ¸Ñ Ñ Ð¿Ð°ÑÐ¸ÐµÐ½ÑÐ¾Ð¼ Ð¿Ð¾ÑÐ»Ðµ ÑÐ°Ð´Ð¸Ð¾Ð½ÑÐºÐ»Ð¸Ð´Ð½Ð¾Ð¹ ÑÐµÑÐ°Ð¿Ð¸Ð¸ Ñ Ð¿ÑÐ¸Ð¼ÐµÐ½ÐµÐ½Ð¸ÐµÐ¼ Lu-177, Sm-153, Sr-89 Ð¸ I-131 Ð¸ Ñ ÑÑÐµÑÐ¾Ð¼ Ð¾Ð±ÑÐ°Ð·Ð¾Ð²Ð°Ð½Ð¸Ñ ÑÐ°Ð´Ð¸Ð¾Ð°ÐºÑÐ¸Ð²Ð½ÑÑ Ð±Ð¸Ð¾Ð»Ð¾Ð³Ð¸ÑÐµÑÐºÐ¸Ñ Ð¾ÑÑÐ¾Ð´Ð¾Ð². ÐÐ°Ð´Ð°ÑÐ¸: 1. ÐÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ Ð¿ÑÐ¾Ð´Ð¾Ð»Ð¶Ð¸ÑÐµÐ»ÑÐ½Ð¾ÑÑÐ¸ Ð¿ÑÐµÐ±ÑÐ²Ð°Ð½Ð¸Ñ Ð¿Ð°ÑÐ¸ÐµÐ½ÑÐ¾Ð² Ð¿Ð¾ÑÐ»Ðµ ÑÐ°Ð´Ð¸Ð¾Ð½ÑÐºÐ»Ð¸Ð´Ð½Ð¾Ð¹ ÑÐµÑÐ°Ð¿Ð¸Ð¸ Ñ Lu-177, Sm-153, Sr-89 Ð¸ I-131, Ð½ÐµÐ¾Ð±ÑÐ¾Ð´Ð¸Ð¼Ð¾Ð³Ð¾ Ð´Ð»Ñ Ð¾Ð±ÐµÑÐ¿ÐµÑÐµÐ½Ð¸Ñ ÑÐ°Ð´Ð¸Ð°ÑÐ¸Ð¾Ð½Ð½Ð¾Ð¹ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ Ð½Ð°ÑÐµÐ»ÐµÐ½Ð¸Ñ Ð½Ð° Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ð¸ ÑÑÑÐµÑÑÐ²ÑÑÑÐ¸Ñ Ð¿Ð¾Ð´ÑÐ¾Ð´Ð¾Ð². 2. ÐÑÐµÐ½ÐºÐ° Ð²Ð¾Ð·Ð´ÐµÐ¹ÑÑÐ²Ð¸Ñ Ð¸Ð·Ð»ÑÑÐµÐ½Ð¸Ñ Ð¾Ñ Ð¿Ð°ÑÐ¸ÐµÐ½ÑÐ° Ð¸ ÐµÐ³Ð¾ Ð¾ÑÑÐ¾Ð´Ð¾Ð² Ð½Ð° Ð»Ð¸Ñ Ð¸Ð· ÐºÐ°ÑÐµÐ³Ð¾ÑÐ¸Ð¹ Ð½Ð°ÑÐµÐ»ÐµÐ½Ð¸Ñ Ð¿ÑÐ¸ ÑÐ°Ð·Ð½ÑÑ ÑÑÐµÐ½Ð°ÑÐ¸ÑÑ Ð²ÑÐ¿Ð¸ÑÐºÐ¸ Ð¿Ð°ÑÐ¸ÐµÐ½ÑÐ¾Ð². 3.ÐÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ ÑÑÐµÐ±Ð¾Ð²Ð°Ð½Ð¸Ð¹ Ðº Ð²ÑÐ¿Ð¸ÑÐºÐµ Ð¿Ð¾ÑÐ»Ðµ ÑÐ°Ð´Ð¸Ð¾Ð½ÑÐºÐ»Ð¸Ð´Ð½Ð¾Ð¹ ÑÐµÑÐ°Ð¿Ð¸Ð¸. Ð ÑÐ¾Ð´Ðµ Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÑ Ð±ÑÐ»Ð° Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð° Ð¾ÑÐµÐ½ÐºÐ° Ð´Ð¾Ð· Ð¾Ñ Ð¾Ð±ÑÐ°Ð·Ð¾Ð²Ð°Ð²ÑÐ¸ÑÑÑ ÑÐ°Ð´Ð¸Ð¾Ð°ÐºÑÐ¸Ð²Ð½ÑÑ Ð¾ÑÑÐ¾Ð´Ð¾Ð² Ð² ÑÐµÐ·ÐµÑÐ²ÑÐ°ÑÐ°Ñ ÑÑÐ¾ÑÐ½ÑÑ Ð²Ð¾Ð´ ÑÑÐ°Ð½ÑÐ¿Ð¾ÑÑÐ½Ð¾Ð³Ð¾ ÑÑÐµÐ´ÑÑÐ²Ð° Ð´Ð»Ñ ÐºÐ°Ð¶Ð´Ð¾Ð³Ð¾ Ð¸Ð· Ð¿ÑÐµÐ´ÑÑÐ°Ð²Ð»ÐµÐ½Ð½ÑÑ Ð¿ÑÐµÐ¿Ð°ÑÐ°ÑÐ¾Ð². Ð¢Ð°Ðº Ð¶Ðµ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð° Ð¿ÑÐ¾Ð²ÐµÑÐºÐ° ÑÐ¾Ð¾ÑÐ²ÐµÑÑÑÐ²Ð¸Ñ ÐºÑÐ¸ÑÐµÑÐ¸ÑÐ¼ Ð²ÑÐ¿Ð¸ÑÐºÐ¸ Ð¿Ð°ÑÐ¸ÐµÐ½ÑÐ¾Ð², Ð² Ð¾ÑÐ½Ð¾ÑÐµÐ½Ð¸Ð¸ ÑÐ¾Ð´ÐµÑÐ¶Ð°ÑÐµÐ¹ÑÑ Ð°ÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð² ÑÐµÐ»Ðµ Ð¿Ð°ÑÐ¸ÐµÐ½ÑÐ° Ð½Ð° Ð¼Ð¾Ð¼ÐµÐ½Ñ Ð²ÑÐ¿Ð¸ÑÐºÐ¸ Ð¸ Ð´Ð¾Ð·, Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ Ð¾ÐºÑÑÐ¶Ð°ÑÑÐ¸Ð¼Ð¸ Ð»Ð¸ÑÐ°Ð¼Ð¸ Ð² ÑÑÐ°Ð½ÑÐ¿Ð¾ÑÑÐµ Ð¸ Ð² Ð¾ÑÐ´ÐµÐ»ÑÐ½Ð¾ ÑÐ°ÑÑÐ¼Ð¾ÑÑÐµÐ½Ð½ÑÑ ÑÐ»ÑÑÐ°ÑÑ ÑÐ¾Ð³Ð»Ð°ÑÐ½Ð¾ Ð½Ð¾ÑÐ¼Ð°ÑÐ¸Ð²Ð°Ð¼ ÐÐ Ð - 99/2009 [1].
description: The purpose of this work is to scientifically substantiate the radiological criteria for discharge, taking into account the exposure of various categories of persons in contact with the patient after radionuclide therapy with Lu-177, Sm-153, Sr-89 and I-131 in view the formation of radioactive biological waste. Tasks: 1. Determination of the length of stay of patients after radionuclide therapy with Lu-177, Sm-153, Sr-89 and I-131, necessary to ensure radiation safety of the population based on existing approaches. 2. Assessment of the effects of radiation from the patient and his waste on persons from population categories under different scenarios of patient discharge. 3. Determination of discharge requirements after radionuclide therapy. In the course of this work, the doses from the radioactive waste generated in wastewater tanks of the vehicle for each of the presented preparations were evaluated. A check of compliance with the criteria for discharge of patients was also carried out, in relation to the activity contained in the patients body at the time of discharge and the doses received by others in transport, and in separately considered cases, according to the standards NRB - 99/2009 [1].