title: Ð Ð°ÑÑÐµÑ Ð¸ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ ÑÐ¸ÑÑÐµÐ¼Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ
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: Calculation and design of the emergency protection system
Creators: name: ÐÑÐ¸Ð½ÑÐº, ÐÑÑÑ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: 2022
Subjects: Ð¯Ð´ÐµÑÐ½ÑÐµ ÑÐµÐ°ÐºÑÐ¾ÑÑ
ÑÐ¸ÑÑÐµÐ¼Ð° ÑÐ¿ÑÐ°Ð²Ð»ÐµÐ½Ð¸Ñ Ð¸ Ð·Ð°ÑÐ¸ÑÑ
ÑÐµÐ°ÐºÑÐ¸Ð²Ð½Ð¾ÑÑÑ
Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ
elements of control and protection system
reactivity
neutron-physical calculation

description: Ð¢ÐµÐ¼Ð° Ð²ÑÐ¿ÑÑÐºÐ½Ð¾Ð¹ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÑ: Â«Ð Ð°ÑÑÐµÑ Ð¸ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ ÑÐ¸ÑÑÐµÐ¼Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑÂ». ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÑÐ¸Ð¿Ð° ÐÐÐ­Ð  Ð¸ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð¾ÑÐ³Ð°Ð½Ð¾Ð² ÑÐµÐ³ÑÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ. 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: ÐÐ·ÑÑÐµÐ½Ð¸Ðµ ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ñ ÑÑÐµÐ±Ð¾Ð²Ð°Ð½Ð¸Ð¹, Ð¿ÑÐµÐ´ÑÑÐ²Ð»ÑÐµÐ¼ÑÑ Ðº ÑÐ¸ÑÑÐµÐ¼Ð°Ð¼ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ. ÐÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð¸ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ ÑÐ¸Ð¿Ð° Ð¸ ÐºÐ¾Ð»Ð¸ÑÐµÑÑÐ²Ð° Ð¼ÐµÑÐ°Ð½Ð¸ÑÐµÑÐºÐ¸Ñ Ð¾ÑÐ³Ð°Ð½Ð¾Ð² Ð¡Ð£Ð. ÐÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ðµ ÐºÐ¸Ð½ÐµÑÐ¸ÐºÐ¸ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð¿Ð¾ÑÐ»Ðµ Ð²Ð½ÐµÑÐµÐ½Ð¸Ñ Ð²Ð¾Ð·Ð¼ÑÑÐµÐ½Ð¸Ð¹. Ð Ð°ÑÑÐµÑ Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ Ð¼Ð¾ÑÐ½Ð¾ÑÑÐ¸ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð¿Ð¾ÑÐ»Ðµ ÑÑÐ°Ð±Ð°ÑÑÐ²Ð°Ð½Ð¸Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ Ð¸ Ð°Ð½Ð°Ð»Ð¸Ð· ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ¾Ð². Ð Ð°Ð±Ð¾ÑÐ° Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð° Ñ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð½Ð¸ÐµÐ¼ Ð¼ÐµÑÐ¾Ð´Ð¸ÑÐµÑÐºÐ¸Ñ Ð¼Ð°ÑÐµÑÐ¸Ð°Ð»Ð¾Ð² Ð¸ ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸Ð·Ð¸ÑÐ¾Ð²Ð°Ð½Ð½Ð¾Ð¹ Ð»Ð¸ÑÐµÑÐ°ÑÑÑÑ. ÐÑÐ» Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ Ñ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸ÐµÐ¼ Ð¾Ð±Ð¾Ð³Ð°ÑÐµÐ½Ð¸Ñ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð°. Ð¢Ð°ÐºÐ¶Ðµ Ð±ÑÐ»Ð¸ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ñ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÑ Ð¼ÐµÑÐ°Ð½Ð¸ÑÐµÑÐºÐ¸Ñ Ð¾ÑÐ³Ð°Ð½Ð¾Ð² Ð¡Ð£Ð. ÐÑÑÐ¾Ð´Ñ Ð¸Ð· ÑÐ°ÑÑÐµÑÐ¾Ð² Ð±ÑÐ»Ð¾ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¾ ÑÐ¸ÑÐ»ÐµÐ½Ð½Ð¾Ðµ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð°Ð²Ð°ÑÐ¸Ð¹ Ñ Ð²Ð²Ð¾Ð´Ð¾Ð¼ Ð¿Ð¾Ð»Ð¾Ð¶Ð¸ÑÐµÐ»ÑÐ½Ð¾Ð¹ ÑÐµÐ°ÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸.Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð° ÑÐ°ÑÑÑÑÐ½Ð°Ñ Ð¾ÑÐµÐ½ÐºÐ° Ð¸Ð·Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ Ð¼Ð¾ÑÐ½Ð¾ÑÑÐ¸ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð¿Ð¾ÑÐ»Ðµ ÑÑÐ°Ð±Ð°ÑÑÐ²Ð°Ð½Ð¸Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ. Ð§Ð¸ÑÐ»ÐµÐ½Ð½Ð¾Ðµ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½ÑÑ Ð¿ÑÐ¾ÑÐµÑÑÐ¾Ð² Ð¿Ð¾ÐºÐ°Ð·Ð°Ð»Ð¾, ÑÑÐ¾ Ð½Ð°Ð¸Ð±Ð¾Ð»ÐµÐµ ÑÑÐ¶ÐµÐ»ÑÐ¼ ÑÐµÐ¶Ð¸Ð¼Ð¾Ð¼ ÑÐ²Ð»ÑÐµÑÑÑ Ð²ÑÐ±ÑÐ¾Ñ Ð¸ÑÐ¿Ð¾Ð»Ð½Ð¸ÑÐµÐ»ÑÐ½Ð¾Ð³Ð¾ Ð¾ÑÐ³Ð°Ð½Ð° Ð¡Ð£Ð Ð¸Ð· Ð½Ð¸Ð¶Ð½ÐµÐ³Ð¾ Ð¿Ð¾Ð»Ð¾Ð¶ÐµÐ½Ð¸Ñ. Ð Ð°ÑÑÑÑ Ð¿Ð¾ÐºÐ°Ð·Ð°Ð», ÑÑÐ¾ ÑÑÐ¼Ð¼Ð°ÑÐ½ÑÐ¹ ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ Ð²ÐµÑ ÑÑÐµÑÐ¶Ð½ÐµÐ¹ Ð¡Ð£Ð Ð´Ð¾ÑÑÐ°ÑÐ¾ÑÐµÐ½ Ð´Ð»Ñ Ð¿ÐµÑÐµÐ²Ð¾Ð´Ð° ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð² Ð¿Ð¾Ð´ÐºÑÐ¸ÑÐ¸ÑÐµÑÐºÐ¾Ðµ ÑÐ¾ÑÑÐ¾ÑÐ½Ð¸Ðµ Ð² ÑÐ°ÑÑÑÑÐ½ÑÑ ÑÐµÐ¶Ð¸Ð¼Ð°Ñ. ÐÐ°Ð½Ð½ÑÐ¹ Ð¼ÐµÑÐ¾Ð´ Ð¾ÑÐµÐ½ÐºÐ¸ ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð¾ÑÐ³Ð°Ð½Ð¾Ð² Ð¡Ð£Ð Ð¼Ð¾Ð¶ÐµÑ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°ÑÑÑÑ Ð½Ð° Ð½Ð°ÑÐ°Ð»ÑÐ½ÑÑ ÑÑÐ°Ð´Ð¸ÑÑ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ°.
description: The subject of the graduate qualification work is Â«Calculation and design of the emergency protection systemÂ». This work is devoted to the study of emergency protection of a VVER reactor and a rough assessment of the effectiveness of control system. Tasks that were solved during the study: 1. Study of the technical requirements for emergency protection systems. 2. Neutron-physical calculation of the reactor and determination of the type and number of mechanical elements of control system. 3. Investigation of the method of calculating the kinetics of the reactor after the introduction of disturbances. 4. Calculation of the reactor power change after the emergency protection is triggered and analysis of the results. The work was carried out using methodological materials and specialized literature. A neutron-physical calculation of the core was carried out with the determination of fuel enrichment. The parameters of the mechanical organs of the CPS were also determined. Based on the calculations, numerical simulation of accidents with the introduction of positive reactivity was carried out. As a result, graphical representations of the reactor power change after the emergency protection was triggered were obtained. Numerical simulation of emergency processes has shown that the most severe mode is the ejection of the executive body of the control system from the lower position. The calculation showed that the total physical weight of the CPS rods is sufficient to transfer the reactor to a subcritical state in the design modes. This method of evaluating the effectiveness of the control system can be used for rough calculation at the initial stages of the design of the power unit.