title: ÐÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ ÑÑÐ°Ð½ÑÐ¼ÑÑÐ°ÑÐ¸Ð¸ Ð´Ð¾Ð»Ð³Ð¾Ð¶Ð¸Ð²ÑÑÐ¸Ñ ÑÐ°Ð´Ð¸Ð¾Ð°ÐºÑÐ¸Ð²Ð½ÑÑ Ð¾ÑÑ Ð¾Ð´Ð¾Ð² Ð¸ Ð¿ÑÐ¾Ð¸Ð·Ð²Ð¾Ð´ÑÑÐ²Ð° ÐºÐ¾Ð±Ð°Ð»ÑÑÐ° Ð² ÑÐµÐ°ÐºÑÐ¾ÑÐµ ÐÐÐ­Ð -Ð¡ÐÐ
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸ÑÑÐ°
titleType: Subtitle
title: Research of long-lived radioactive waste transmutation and cobalt production efficiency in the VVER-SCD reactor
Creators: name: Ð¯ÑÐ¸Ð½Ð°, ÐÐ»ÐµÐºÑÐ°Ð½Ð´Ñ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: 2023
Subjects: Ð¯Ð´ÐµÑÐ½ÑÐµ ÑÐµÐ°ÐºÑÐ¾ÑÑ Ð²Ð¾Ð´Ð¾-Ð²Ð¾Ð´ÑÐ½ÑÐµ
Ð Ð°Ð´Ð¸Ð¾Ð°ÐºÑÐ¸Ð²Ð½ÑÐµ Ð¾ÑÑ Ð¾Ð´Ñ
Ð¼Ð¸Ð½Ð¾ÑÐ½ÑÐµ Ð°ÐºÑÐ¸Ð½Ð¸Ð´Ñ
ÑÑÐ°Ð½ÑÐ¼ÑÑÐ°ÑÐ¸Ñ ÑÐ°Ð´Ð¸Ð¾Ð°ÐºÑÐ¸Ð²Ð½ÑÑ Ð¾ÑÑ Ð¾Ð´Ð¾Ð²
Ð½Ð°ÑÐ°Ð±Ð¾ÑÐºÐ° ÐºÐ¾Ð±Ð°Ð»ÑÑÐ°-60
minor actinides
radioactive waste transmutation
cobalt-60 production

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° ÑÑÐ°Ð²Ð½ÐµÐ½Ð¸Ñ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐ°ÑÑÐµÑÐ¾Ð² Ð² Ð´Ð²ÑÑ Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ð½ÑÑ Ð¾Ð±ÐµÑÐ¿ÐµÑÐµÐ½Ð¸Ñ, Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑÑÐ°Ð½ÑÐ¼ÑÑÐ°ÑÐ¸Ð¸ Ð´Ð¾Ð»Ð³Ð¾Ð¶Ð¸Ð²ÑÑÐ¸Ñ ÑÐ°Ð´Ð¸Ð¾Ð°ÐºÑÐ¸Ð²Ð½ÑÑ Ð¾ÑÑÐ¾Ð´Ð¾Ð² Ð¸ Ð¾ÑÐµÐ½ÐºÐµ Ð²Ð¾Ð·Ð¼Ð¾Ð¶Ð½Ð¾ÑÑÐ¸ Ð½Ð°ÑÐ°Ð±Ð¾ÑÐºÐ¸ Co-60 Ð² ÑÐµÐ°ÐºÑÐ¾ÑÐµ ÐÐÐ­Ð -Ð¡ÐÐ. ÐÐ°Ð´Ð°ÑÐ¸, ÐºÐ¾ÑÐ¾ÑÑÐµ ÑÐµÑÐ°Ð»Ð¸ÑÑ Ð² ÑÐ¾Ð´Ðµ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ: 1. ÐÐ·ÑÑÐµÐ½Ð¸Ðµ ÑÑÑÐµÑÑÐ²ÑÑÑÐ¸Ñ Ð¿ÑÐ¾ÐµÐºÑÐ¾Ð² ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð² ÑÐ¾ ÑÐ²ÐµÑÑÐºÑÐ¸ÑÐ¸ÑÐµÑÐºÐ¸Ð¼Ð¸ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ°Ð¼Ð¸, Ð²ÑÐ±Ð¾Ñ ÑÐµÑÐµÑÐµÐ½ÑÐ½Ð¾Ð³Ð¾ Ð¿ÑÐ¾ÐµÐºÑÐ°; 2. ÐÐ·ÑÑÐµÐ½Ð¸Ðµ Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ð½Ð¾Ð¹ ÑÑÐµÐ´Ñ SERPENT Ð´Ð»Ñ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ñ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾- ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐ°ÑÑÐµÑÐ¾Ð²; 3. ÐÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ðµ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð³Ð¾ Ð¸ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐ°ÑÑÐµÑÐ¾Ð² Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ ÑÐµÑÐµÑÐµÐ½ÑÐ½Ð¾Ð³Ð¾ Ð¿ÑÐ¾ÐµÐºÑÐ° ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ñ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð½Ð¸ÐµÐ¼ SERPENT; 4. ÐÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ðµ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐ°ÑÑÐµÑÐ° Ð¿ÑÐµÐ´Ð»Ð°Ð³Ð°ÐµÐ¼Ð¾Ð¹ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ Ñ Ð²ÑÐ±ÑÐ°Ð½Ð½ÑÐ¼Ð¸ Ð¢ÐÐ¡ Ð¸ ÑÑÐ°Ð½ÑÐ¼ÑÑÐ°ÑÐ¸Ð¸ Am-241 Ð¸ Ð²Ð¾Ð·Ð¼Ð¾Ð¶Ð½Ð¾ÑÑÐ¸ Ð½Ð°ÑÐ°Ð±Ð¾ÑÐºÐ¸ Co-60 Ð² ÑÐµÐ°ÐºÑÐ¾ÑÐµ ÐÐÐ­Ð -Ð¡ÐÐ. 5. Ð¡ÑÐ°Ð²Ð½ÐµÐ½Ð¸Ðµ Ð¸ Ð°Ð½Ð°Ð»Ð¸Ð· ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ¾Ð², Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ Ð² SERPENT Ð¸ MCU-FREE ÐÑÑÐ¸ÑÐ»ÐµÐ½Ð¸Ñ Ð¿ÑÐ¾Ð¸Ð·Ð²Ð¾Ð´Ð¸Ð»Ð¸ÑÑ Ð² Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ð½Ð¾Ð¹ ÑÑÐµÐ´Ðµ. ÐÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ñ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ðµ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸ Ð¢ÐÐ¡, ÑÐ¾Ð´ÐµÑÐ¶Ð°ÑÐ¸Ñ Ð¸Ð·Ð¾ÑÐ¾Ð¿Ñ Am-241 Ð¸ Co-59 Ð´Ð»Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ ÑÑÐ°ÑÑÐºÐ¾Ð² Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ Ð¸ ÑÐ°ÑÑÑÐ¸ÑÐ°Ð½Ð° ÑÑÐ°Ð½ÑÐ¼ÑÑÐ°ÑÐ¸Ñ Am-241 Ð¸ Ð½Ð°ÑÐ°Ð±Ð¾ÑÐºÐ° Co-60. ÐÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¾ ÑÑÐ°Ð²Ð½ÐµÐ½Ð¸Ðµ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸Ðº ÑÐµÑÐµÑÐµÐ½ÑÐ½Ð¾Ð¹ Ð¸ Ð¿ÑÐµÐ´Ð»Ð°Ð³Ð°ÐµÐ¼Ð¾Ð¹ Ð°ÐºÑÐ¸Ð²Ð½ÑÑ Ð·Ð¾Ð½. Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ Ð±ÑÐ»Ð¸ Ð¿ÑÐ¾Ð°Ð½Ð°Ð»Ð¸Ð·Ð¸ÑÐ¾Ð²Ð°Ð½Ñ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÑ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐ°ÑÑÐµÑÐ° Ð¸ Ð¾ÑÐµÐ½ÐºÐ¸ ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ ÑÑÐ°Ð½ÑÐ¼ÑÑÐ°ÑÐ¸Ð¸ Ð¸ Ð½Ð°ÑÐ°Ð±Ð¾ÑÐºÐ¸ Co-60 Ð² Ð´Ð²ÑÑ Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ð½ÑÑ Ð¾Ð±ÐµÑÐ¿ÐµÑÐµÐ½Ð¸ÑÑ.
description: This work is devoted to the comparison of neutron physics calculations in two software, the study of transmutation of long-lived radioactive waste and the assessment of the possibility of operating Co-60 in the VVER-SKD reactor. The tasks that were solved in the course of this study were: 1. Study of existing projects of reactors with supercritical parameters, selection of a reference project; 2. Study of the SERPENT software environment for conducting neutron physics calculations; 3. Conducting thermal and neutron-physical calculations of the core of the reference reactor design using SERPENT; 4. Conducting a neutron-physical calculation of the proposed core with selected fuel assemblies and Am-241 transmutation and the possibility of operating Co-60 in the VVER-SKD reactor. 5. Comparison and analysis of the results obtained in SERPENT and MCU-FREE The calculations were performed in a software environment. The neutron-physical characteristics of fuel assemblies containing isotopes Am-241 and Co-59 for various parts of the core were determined and the transmutation of Am-241 and the operating time of Co-60 were evaluated. The neutron-physical characteristics of the reference and proposed active zones are compared. As a result, the results of neutron-physical calculation and evaluation of the efficiency of transmutation and the development of Co-60 in two software were analyzed.As a result, the transmutation of Am-241 and of operating Co-60 and their influence on the neutron-physical characteristics of reactor have been analyzed and confirmed.