title: ÐÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð²Ð¾Ð´Ð¾-Ð²Ð¾Ð´ÑÐ½Ð¾Ð³Ð¾ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÑÐ¾ ÑÐ¿ÐµÐºÑÑÐ°Ð»ÑÐ½ÑÐ¼ ÑÐµÐ³ÑÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸ÐµÐ¼ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ð¹ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 600 ÐÐÑ (ÐÐÐ­Ð â600Ð¡)
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: Design of a water-water energeticreactor of electric power of 600 MW with spectral regulation (WWERâ600S)
Creators: name: ÐÐ¸ÐºÐ¾Ð»Ð°ÐµÐ², ÐÑÑÑÐ¼
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: Ð²Ð¾Ð´Ð¾-Ð²Ð¾Ð´ÑÐ½Ð¾Ð¹ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¸Ð¹ ÑÐµÐ°ÐºÑÐ¾Ñ
ÑÐ¿ÐµÐºÑÑÐ°Ð»ÑÐ½Ð¾Ðµ ÑÐµÐ³ÑÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ
Ð²Ð¾Ð´Ð¾-ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ðµ Ð¾ÑÐ½Ð¾ÑÐµÐ½Ð¸Ðµ
ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÑÑ
Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÑÑ ÐÐÐ­Ð
water-water energetic reactor
spectral regulation
water-fuel ratio
thermohydraulic calculation
neutron-physical calculation of WWER

description: Ð Ð°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð²Ð¾Ð´Ð¾-Ð²Ð¾Ð´ÑÐ½Ð¾Ð³Ð¾ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÑÐ¾ ÑÐ¿ÐµÐºÑÑÐ°Ð»ÑÐ½ÑÐ¼ ÑÐµÐ³ÑÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸ÐµÐ¼ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ð¹ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 600 ÐÐÑ (ÐÐÐ­Ð â600Ð¡). ÐÐ°Ð´Ð°ÑÐ¸, ÐºÐ¾ÑÐ¾ÑÑÐµ ÑÐµÑÐ°Ð»Ð¸ÑÑ Ð² ÑÐ¾Ð´Ðµ ÑÐ°ÑÑÑÑÐ°:1. ÐÐ½Ð°Ð»Ð¸Ð· ÑÐ¿Ð¾ÑÐ¾Ð±Ð¾Ð² ÑÐ¿ÐµÐºÑÑÐ°Ð»ÑÐ½Ð¾Ð³Ð¾ ÑÐµÐ³ÑÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°;2. Ð¢ÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÑÑ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°;3. ÐÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÑÑ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ Ð´Ð»Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ Ð·Ð½Ð°ÑÐµÐ½Ð¸Ð¹ Ð²ÐµÐ»Ð¸-ÑÐ¸Ð½ Ð²Ð¾Ð´Ð¾-ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ð³Ð¾ Ð¾ÑÐ½Ð¾ÑÐµÐ½Ð¸Ñ;4. ÐÐ¾Ð½ÑÑÑÑÐºÑÐ¸Ð²Ð½ÑÐ¹ Ð¿ÑÐ¾ÑÐ½Ð¾ÑÑÐ½Ð¾Ð¹ ÑÐ°ÑÑÑÑ ÐºÐ¾ÑÐ¿ÑÑÐ° ÑÐµÐ°ÐºÑÐ¾ÑÐ°.Ð ÑÐ¾Ð´Ðµ Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð¸Ñ ÑÐ°Ð±Ð¾ÑÑ Ð¸Ð·ÑÑÐµÐ½Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÐµ ÑÐ¿Ð¾ÑÐ¾Ð±Ñ ÑÐ¿ÐµÐºÑÑÐ°Ð»ÑÐ½Ð¾Ð³Ð¾ ÑÐ¿ÑÐ°Ð²-Ð»ÐµÐ½Ð¸Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð¼ Ð·Ð° ÑÑÑÑ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ Ð²Ð¾Ð´Ð½Ð¾-ÑÑÐ°Ð½Ð¾Ð²Ð¾Ð³Ð¾ ÑÐ¾Ð¾ÑÐ½Ð¾ÑÐµÐ½Ð¸Ñ. ÐÑÐ¸Ð½ÑÑÐ¾ Ð¸ÑÐ¿Ð¾Ð»Ñ-Ð·Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð²ÑÑÐµÑÐ½Ð¸ÑÐµÐ»ÐµÐ¹, Ð¸Ð·Ð¼ÐµÐ½ÑÑÑÐ¸Ñ ÑÐ²Ð¾Ñ ÑÐ°ÑÐ¿Ð¾Ð»Ð¾Ð¶ÐµÐ½Ð¸Ðµ Ð² Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ðµ Ð² ÑÐ¾Ð´Ðµ ÐºÐ°Ð¼-Ð¿Ð°Ð½Ð¸Ð¸. ÐÑÐµÐ´Ð»Ð¾Ð¶ÐµÐ½Ñ Ð²Ð°ÑÐ¸Ð°Ð½ÑÑ ÐºÐ¾Ð¼Ð¿Ð¾Ð½Ð¾Ð²ÐºÐ¸ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ Ð¸ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ñ Ð¸Ñ Ð³ÐµÐ¾Ð¼ÐµÑ-ÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸. ÐÐ¾ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ°Ð¼ ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐ°ÑÑÑÑÐ° Ð¾Ð¿ÑÐµÐ´ÐµÐ»Ðµ-Ð½Ñ ÑÐ½ÐµÑÐ³Ð¾Ð½Ð°Ð¿ÑÑÐ¶ÑÐ½Ð½Ð¾ÑÑÑ ÐÐ, ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ Ð¸ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°, Ð° ÑÐ°ÐºÐ¶Ðµ Ð¿Ð¾ÑÐµÑÐ¸ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ñ Ð¿Ð¾ Ð¿ÐµÑÐ²Ð¾Ð¼Ñ ÐºÐ¾Ð½ÑÑÑÑ Ð¯Ð­Ð£ Ð´Ð»Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ Ð²Ð°ÑÐ¸Ð°Ð½ÑÐ¾Ð². ÐÐ¾ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ°Ð¼ ÑÑÐ°Ð²-Ð½Ð¸ÑÐµÐ»ÑÐ½Ð¾Ð³Ð¾ Ð°Ð½Ð°Ð»Ð¸Ð·Ð° Ð²ÑÐ±ÑÐ°Ð½Ð° ÐºÐ¾Ð¼Ð¿Ð¾Ð½Ð¾Ð²ÐºÐ°, ÑÐ¾ÑÑÐ¾ÑÑÐ°Ñ Ð¸Ð· 121 Ð¢ÐÐ¡. ÐÑÐ¾Ð²ÐµÐ´ÑÐ½ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÑÑ. Ð Ð°ÑÑÑÐ¸ÑÐ°Ð½Ð¾ ÑÐ°Ð±Ð¾ÑÐµÐµ Ð¾Ð±Ð¾Ð³Ð°ÑÐµÐ½Ð¸Ðµ Ð¸ Ð³Ð»ÑÐ±Ð¸Ð½Ð° Ð²ÑÐ³Ð¾ÑÐ°Ð½Ð¸Ñ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°. ÐÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð° Ð¾ÑÐµÐ½ÐºÐ° Ð½ÐµÐ¾Ð±ÑÐ¾Ð´Ð¸Ð¼Ð¾Ð³Ð¾ ÐºÐ¾Ð»Ð¸ÑÐµÑÑÐ²Ð° Ð¼ÐµÑÐ°Ð½Ð¸ÑÐµÑÐºÐ¸Ñ Ð¾ÑÐ³Ð°Ð½Ð¾Ð² ÑÐµÐ³Ñ-Ð»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¡Ð£Ð. ÐÑÐ¿Ð¾Ð»Ð½ÐµÐ½ ÐºÐ¾Ð½ÑÑÑÑÐºÑÐ¸Ð²Ð½ÑÐ¹ ÑÐ°ÑÑÑÑ Ð½Ð° Ð¿ÑÐ¾ÑÐ½Ð¾ÑÑÑ ÐºÐ¾ÑÐ¿ÑÑÐ° ÑÐµÐ°ÐºÑÐ¾ÑÐ°. ÐÑÐ¾Ð°Ð½Ð°Ð»Ð¸Ð·Ð¸ÑÐ¾Ð²Ð°Ð½Ð¾ Ð²Ð»Ð¸ÑÐ½Ð¸Ðµ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ Ð²Ð¾Ð´Ð½Ð¾-ÑÑÐ°Ð½Ð¾Ð²Ð¾Ð³Ð¾ Ð¾ÑÐ½Ð¾ÑÐµÐ½Ð¸Ñ Ð½Ð° ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸-ÑÑÐ¸ÐºÐ¸ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ.
description: The work is devoted to the design of a water-water power reactor with spectral regu-lation with an electrical capacity of 600 MW (WWERâ600S). The tasks to solve during the calculation were:1. Analysis of methods of spectral regulation of the reactor;2. Thermohydraulic calculation of the reactor core;3. Neutron-physical calculation of the core for various values of the water-fuel ratio;4. Structural strength calculation of the reactor vessel.In the course of the work, various methods of spectral control of the reactor were studied by changing the water-uranium ratio. It was taken to use displacers that change their location in the reactor core during the campaign. Variants of the core layout were proposed and their geometric characteristics were determined. Based on the results of the thermohydraulic calculation, the core power density, the temperatures of the coolant and fuel, as well as pressure losses along the primary circuit of the nuclear power plant for dif-ferent variants were determined. Based on the results of a comparative analysis, a layout consisting of 121 fuel assemblies was chosen. A neutron-physical calculation was carried out. The working enrichment and the depth of fuel burn-up are calculated. An assessment of the required number of mechanical controls of the CPS was carried out. A constructive calculation for the strength of the reactor vessel was performed. The influence of changes in the water-uranium ratio on the characteristics of the core was analyzed.