title: Ð Ð°ÑÑÐµÑÐ½ÑÐ¹ Ð°Ð½Ð°Ð»Ð¸Ð· ÑÐ°Ð·ÑÑÐ²Ð¾Ð² ÑÑÑÐ±Ð¾Ð¿ÑÐ¾Ð²Ð¾Ð´Ð¾Ð², ÑÐ¾Ð´ÐµÑÐ¶Ð°ÑÐ¸Ñ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ Ð¿ÐµÑÐ²Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÑÑÐ°, Ð² ÑÐ°Ð¼ÐºÐ°Ñ Ð´ÐµÑÐµÑÐ¼Ð¸Ð½Ð¸ÑÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð°Ð½Ð°Ð»Ð¸Ð·Ð° Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ ÐÐ­Ð¡
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: Computational analysis of pipeline rupture containing primary coolant of nuclear power plants based on deterministic safety assessment
Creators: name: ÐÐµÑÐµÐ¿ÐºÐ¾, Ð¯Ð½Ð°
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ÑÐ¾Ð¼Ð½ÑÐµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÑÐ°Ð½ÑÐ¸Ð¸
Ð¯Ð´ÐµÑÐ½ÑÐµ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸
Ð¢ÑÑÐ±Ð¾Ð¿ÑÐ¾Ð²Ð¾Ð´Ñ
Ð¼ÐµÑÐ¾Ð´Ð¸ÐºÐ° ÑÐ°ÑÑÐµÑÐ°
ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ
methodology of calculation
thermal-hydraulic calculations

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° ÑÐ°Ð·ÑÐ°Ð±Ð¾ÑÐºÐµ Ð¸ Ð°Ð¿ÑÐ¾Ð±Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¼ÐµÑÐ¾Ð´Ð¸ÐºÐ¸ ÑÐ°ÑÑÐµÑÐ° ÑÐ»ÑÑÑÐ¾Ð²Ð¾Ð³Ð¾ Ð´Ð²Ð¸Ð¶ÐµÐ½Ð¸Ñ ÑÑÑÐ±Ð¾Ð¿ÑÐ¾Ð²Ð¾Ð´Ð° Ð¿Ð¾Ð´ Ð´ÐµÐ¹ÑÑÐ²Ð¸ÐµÐ¼ Ð³Ð¸Ð´ÑÐ¾Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¸Ñ ÑÑÐ¸Ð»Ð¸Ð¹, Ð²Ð¾Ð·Ð½Ð¸ÐºÐ°ÑÑÐ¸Ñ Ð¿ÑÐ¸ ÑÐ°Ð·ÑÑÐ²Ð°Ñ Ð²ÑÑÐ¾ÐºÐ¾ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¸Ñ ÑÑÑÐ±Ð¾Ð¿ÑÐ¾Ð²Ð¾Ð´Ð¾Ð², ÑÐ¾Ð´ÐµÑÐ¶Ð°ÑÐ¸Ñ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ Ð¿ÐµÑÐ²Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÑÑÐ°, Ð² ÑÐ°Ð¼ÐºÐ°Ñ Ð´ÐµÑÐµÑÐ¼Ð¸Ð½Ð¸ÑÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð°Ð½Ð°Ð»Ð¸Ð·Ð° Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ ÐÐ­Ð¡. ÐÐ°Ð´Ð°ÑÐ¸, ÑÐµÑÐ°ÐµÐ¼ÑÐµ Ð² ÑÐ¾Ð´Ðµ ÑÐ°Ð±Ð¾ÑÑ: 1. ÐÐ½Ð°Ð»Ð¸Ð· ÑÑÐµÐ±Ð¾Ð²Ð°Ð½Ð¸Ð¹ Ð½Ð¾ÑÐ¼Ð°ÑÐ¸Ð²Ð½ÑÑ Ð´Ð¾ÐºÑÐ¼ÐµÐ½ÑÐ¾Ð² Ðº Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ñ Ð´ÐµÑÐµÑÐ¼Ð¸Ð½Ð¸ÑÑÐ¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð°Ð½Ð°Ð»Ð¸Ð·Ð° Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸, Ð² ÑÐ¾Ð¼ ÑÐ¸ÑÐ»Ðµ Ð² ÑÐ°ÑÑÐ¸ Ð°Ð½Ð°Ð»Ð¸Ð·Ð° ÑÐ³ÑÐ¾Ð·. 2. ÐÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ Ð¾Ð±ÑÐµÐ¹ Ð¼ÐµÑÐ¾Ð´Ð¸ÐºÐ¸ ÑÐ°ÑÑÐµÑÐ°. 3. ÐÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ðµ ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐ°ÑÑÐµÑÐ° ÑÐ¸ÑÑÐµÐ¼Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð³Ð¾ ÑÐ°ÑÑÐ¾Ð»Ð°Ð¶Ð¸Ð²Ð°Ð½Ð¸Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°; Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ Ð½Ð°Ð³ÑÑÐ·Ð¾Ðº Ð½Ð° Ð¾ÑÐ²Ð¾Ð´Ñ ÑÑÑÐ±Ð¾Ð¿ÑÐ¾Ð²Ð¾Ð´Ð½Ð¾Ð¹ ÑÑÐ°ÑÑÑ Ð´Ð»Ñ ÐºÐ°Ð¶Ð´Ð¾Ð³Ð¾ Ð¸Ð· Ð¿Ð¾ÑÑÑÐ»Ð¸ÑÑÐµÐ¼ÑÑ Ð¼ÐµÑÑ ÑÐ°Ð·ÑÑÐ²Ð¾Ð². 4. ÐÐ¾ÑÑÑÐ¾ÐµÐ½Ð¸Ðµ ÑÐ°ÑÑÐµÑÐ½Ð¾Ð¹ Ð¼Ð¾Ð´ÐµÐ»Ð¸ Ð¸ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ðµ Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ ÑÐ°ÑÑÐµÑÐ°. 5. Ð¡Ð¾ÑÑÐ°Ð²Ð»ÐµÐ½Ð¸Ðµ Ð¿ÐµÑÐµÑÐ½Ñ Ð¿Ð¾Ð²ÑÐµÐ¶Ð´ÐµÐ½Ð½ÑÑ ÑÐ¸ÑÑÐµÐ¼, ÐºÐ¾Ð¼Ð¿Ð¾Ð½ÐµÐ½ÑÐ¾Ð², ÐºÐ¾Ð½ÑÑÑÑÐºÑÐ¸Ð¹ (Ð¡ÐÐ); Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ Ð²Ð»Ð¸ÑÐ½Ð¸Ñ Ð¿Ð¾ÑÐµÑÐ¸ Ð´Ð°Ð½Ð½ÑÑ Ð¡ÐÐ Ð½Ð° Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÑ ÐÐ­Ð¡. 6. ÐÐ½Ð°Ð»Ð¸Ð· Ð¾Ð±ÑÐµÐ¼Ð° Ð¸ÑÑÐ¾Ð´Ð½ÑÑ Ð´Ð°Ð½Ð½ÑÑ, ÑÑÐµÐ±ÑÐµÐ¼ÑÑ Ð´Ð»Ñ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ñ Ð½Ð°ÑÑÐ¾ÑÑÐµÐ³Ð¾ Ð°Ð½Ð°Ð»Ð¸Ð·Ð°; Ð¾ÑÐµÐ½ÐºÐ° ÑÑÑÐ´Ð¾Ð·Ð°ÑÑÐ°Ñ Ð¸ ÑÑÐµÐ±ÑÐµÐ¼ÑÑ ÐºÐ¾Ð¼Ð¿ÐµÑÐµÐ½ÑÐ¸Ð¹ ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸ÑÑÐ¾Ð². Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ ÑÐ°Ð±Ð¾ÑÑ Ð±ÑÐ»Ð° ÑÐ°Ð·ÑÐ°Ð±Ð¾ÑÐ°Ð½Ð° Ð¼ÐµÑÐ¾Ð´Ð¸ÐºÐ°, ÐºÐ¾ÑÐ¾ÑÐ°Ñ Ð¼Ð¾Ð¶ÐµÑ Ð±ÑÑÑ Ð¿ÑÐµÐ´Ð»Ð¾Ð¶ÐµÐ½Ð° Ðº Ð¿ÑÐ¸Ð¼ÐµÐ½ÐµÐ½Ð¸Ñ ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸ÑÑÐ°Ð¼ ÐÐ Â«ÐÐ¢ÐÐÐ­ÐÐÐ ÐÐÐÐ ÐÐÐÐ¢Â». ÐÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð½Ð¸Ðµ ÑÐºÐ°Ð·Ð°Ð½Ð½Ð¾Ð¹ Ð¼ÐµÑÐ¾Ð´Ð¸ÐºÐ¸ Ð¿Ð¾Ð·Ð²Ð¾Ð»Ð¸Ñ Ð¿Ð¾Ð²ÑÑÐ¸ÑÑ ÐºÐ°ÑÐµÑÑÐ²Ð¾ ÑÐ°ÑÑÐµÑÐ½Ð¾Ð³Ð¾ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ñ Ð¸ ÑÐ½ÑÑÑ Ð¸Ð·Ð±ÑÑÐ¾ÑÐ½ÑÐ¹ ÐºÐ¾Ð½ÑÐµÑÐ²Ð°ÑÐ¸Ð·Ð¼ Ð¿ÑÐ¸ ÑÐ°Ð·ÑÐ°Ð±Ð¾ÑÐºÐµ ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ñ ÑÐµÑÐµÐ½Ð¸Ð¹ Ð¸ ÑÐµÐ¼ ÑÐ°Ð¼ÑÐ¼ ÑÐ½Ð¸Ð·Ð¸ÑÑ ÐºÐ°Ð¿Ð¸ÑÐ°Ð»ÑÐ½ÑÐµ Ð·Ð°ÑÑÐ°ÑÑ Ð½Ð° ÑÐ¾Ð¾ÑÑÐ¶ÐµÐ½Ð¸Ðµ ÐÐ­Ð¡.
description: The present work is devoted to the development and testing of a methodology for calculating the whiplash displacement of a pipeline in presence of hydrodynamic forces arising from ruptures of high-energy pipelines containing a primary coolant within the context of deterministic analysis of NPP safety. The considered tasks can be listed as follows: 1. Analysis of the requirements of regulatory documents for conducting deterministic safety analysis, including risk analysis. 2. Determination of the general calculation methodology. 3. Performing the thermal-hydraulic evaluation of the reactor emergency cooling system; determining the loads on the bends of the pipeline route for each of the postulated rupture places. 4. Developing a computational model and performing dynamic calculations. 5. Providing a list of damaged systems, components, structures (SCS); determining the impact of SCS data loss on NPP safety. 6. Estimation of the amount of initial data required for this analysis; assessment of labor costs and required competencies of specialists. As a result of the work, a methodology has been developed that can be proposed for being employed by specialists of ATOMENERGOPROEKT JSC. The use of this technique will improve the quality of the calculation justification and remove excessive conservatism in the development of technical solutions and thereby reduce NPP capital costs.