РабоÑа поÑвÑÑена пÑоекÑиÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð²Ð¾Ð´Ð¾-водÑного ÑнеÑгеÑиÑеÑкого ÑеакÑоÑа Ñо ÑпекÑÑалÑнÑм ÑегÑлиÑованием ÑлекÑÑиÑеÑкой моÑноÑÑÑÑ 600 ÐÐÑ (ÐÐÐÐ â600С). ÐадаÑи, коÑоÑÑе ÑеÑалиÑÑ Ð² Ñ Ð¾Ð´Ðµ ÑаÑÑÑÑа:1. Ðнализ ÑпоÑобов ÑпекÑÑалÑного ÑегÑлиÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑеакÑоÑа;2. ТеплогидÑавлиÑеÑкий ÑаÑÑÑÑ Ð°ÐºÑивной Ð·Ð¾Ð½Ñ ÑеакÑоÑа;3. ÐейÑÑонно-ÑизиÑеÑкий ÑаÑÑÑÑ Ð°ÐºÑивной Ð·Ð¾Ð½Ñ Ð´Ð»Ñ ÑазлиÑнÑÑ Ð·Ð½Ð°Ñений вели-Ñин водо-Ñопливного оÑноÑениÑ;4. ÐонÑÑÑÑкÑивнÑй пÑоÑноÑÑной ÑаÑÑÑÑ ÐºÐ¾ÑпÑÑа ÑеакÑоÑа.Ð Ñ Ð¾Ð´Ðµ вÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð¸Ñ ÑабоÑÑ Ð¸Ð·ÑÑÐµÐ½Ñ ÑазлиÑнÑе ÑпоÑÐ¾Ð±Ñ ÑпекÑÑалÑного ÑпÑав-Ð»ÐµÐ½Ð¸Ñ ÑеакÑоÑом за ÑÑÑÑ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ Ð²Ð¾Ð´Ð½Ð¾-ÑÑанового ÑооÑноÑениÑ. ÐÑинÑÑо иÑполÑ-зование вÑÑеÑниÑелей, изменÑÑÑÐ¸Ñ ÑÐ²Ð¾Ñ ÑаÑположение в акÑивной зоне в Ñ Ð¾Ð´Ðµ кам-пании. ÐÑÐµÐ´Ð»Ð¾Ð¶ÐµÐ½Ñ Ð²Ð°ÑианÑÑ ÐºÐ¾Ð¼Ð¿Ð¾Ð½Ð¾Ð²ÐºÐ¸ акÑивной Ð·Ð¾Ð½Ñ Ð¸ опÑÐµÐ´ÐµÐ»ÐµÐ½Ñ Ð¸Ñ Ð³ÐµÐ¾Ð¼ÐµÑ-ÑиÑеÑкие Ñ Ð°ÑакÑеÑиÑÑики. Ðо ÑезÑлÑÑаÑам ÑеплогидÑавлиÑеÑкого ÑаÑÑÑÑа опÑеделе-Ð½Ñ ÑнеÑгонапÑÑжÑнноÑÑÑ ÐÐ, ÑемпеÑаÑÑÑÑ ÑеплоноÑиÑÐµÐ»Ñ Ð¸ Ñоплива, а Ñакже поÑеÑи Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ñ Ð¿Ð¾ пеÑÐ²Ð¾Ð¼Ñ ÐºÐ¾Ð½ÑÑÑÑ Ð¯ÐУ Ð´Ð»Ñ ÑазлиÑнÑÑ Ð²Ð°ÑианÑов. Ðо ÑезÑлÑÑаÑам ÑÑав-ниÑелÑного анализа вÑбÑана компоновка, ÑоÑÑоÑÑÐ°Ñ Ð¸Ð· 121 ТÐС. ÐÑоведÑн нейÑÑонно-ÑизиÑеÑкий ÑаÑÑÑÑ. РаÑÑÑиÑано ÑабоÑее обогаÑение и глÑбина вÑгоÑÐ°Ð½Ð¸Ñ Ñоплива. ÐÑоведена оÑенка Ð½ÐµÐ¾Ð±Ñ Ð¾Ð´Ð¸Ð¼Ð¾Ð³Ð¾ колиÑеÑÑва Ð¼ÐµÑ Ð°Ð½Ð¸ÑеÑÐºÐ¸Ñ Ð¾Ñганов ÑегÑ-лиÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¡Ð£Ð. ÐÑполнен конÑÑÑÑкÑивнÑй ÑаÑÑÑÑ Ð½Ð° пÑоÑноÑÑÑ ÐºÐ¾ÑпÑÑа ÑеакÑоÑа. ÐÑоанализиÑовано влиÑние Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ Ð²Ð¾Ð´Ð½Ð¾-ÑÑанового оÑноÑÐµÐ½Ð¸Ñ Ð½Ð° Ñ Ð°ÑакÑеÑи-ÑÑики акÑивной зонÑ. The work is devoted to the design of a water-water power reactor with spectral regu-lation with an electrical capacity of 600 MW (WWERâ600S). 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.
