Published October 1982
| Version v1
Journal article
On the calculation of dynamic stresses in reactor supporting structures
Description
The problem of calculating NPP equipment reliability at maximum credible accident (instant blowdown of the primary circuit pipelines) is considered. The solution to the problem is considered as applied to the system reactor-upper unit connected by supporting elements with concrete structures of the well. Basing on the analysis of calculation results exercised for a WWER-440 reactor it is concluded that the highest dynamical stresses in the vessel supports are developed in 0.2-0.53 after an accident
Additional details
Additional titles
- Original title (Russian)
- О расчете динамических усилий в опорных конструкциях реактора
Publishing Information
- Journal Title
- Ehnergomashinostroenie
- Journal Issue
- no.10
- Series
- Ehnergomashinostroenie.
- ISSN
- 0131-1336
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 15010051
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALGORITHMS; DYNAMIC LOADS; LOSS OF COOLANT; MECHANICAL VIBRATIONS; NUMERICAL SOLUTION; PIPELINES; PRIMARY COOLANT CIRCUITS; REACTOR VESSELS; RUPTURES; STRESSES; SUPPORTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; MECHANICAL STRUCTURES; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS