Analysis of thermo-hydraulic stability in the channels of a boiling water-cooled reactor
Description
A technique for calculating thermohydraulic stability in steam-generating channels of a boiling reactor is considered. The technique is based on the stability analysis of one-dimension nonstationary model of fluid flow including linearized equations of continuity, pulse and energy. Equations describing local resistances are coupled on the base of dependence for pressure losses due to local resistance. Set of equations of thermohydraulics is closed-up by a series of empirical dependences for hydraulic friction, real steam content and others which are considered as quasistationary. Roots of characteristic equation are analyzed by the D sharing method. The RAGU computer code realizing the given calculation technique has been made using ALGOL language for the BESM-6 computer. The results of calculation according to the RAGU program are compared with experimental data on stability boundaries in the model of RBMK-1500 channel path. Good agreement of such calculations and experimental data has been obtained
Additional details
Additional titles
- Original title (Russian)
- Анализ теплогидравлической устойчивости в каналах кипящего реактора
Publishing Information
- Journal Title
- At. Ehnerg.
- Journal Volume
- 48
- Journal Issue
- 6
- Series
- At. Ehnerg.
- Journal Page Range
- 366-369
- ISSN
- 0004-7163
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 12585773
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BOILING; BOUNDARY CONDITIONS; COMPUTER CALCULATIONS; ENTHALPY; FLUID FLOW; FRICTION; HEAT FLUX; HEAT TRANSFER; HIGH TEMPERATURE; HYDRAULICS; LWGR TYPE REACTORS; MEDIUM PRESSURE; ONE-DIMENSIONAL CALCULATIONS; REACTOR CHANNELS; STABILITY; TEMPERATURE DEPENDENCE; THERMAL BOUNDARY RESISTANCE; TWO-PHASE FLOW
- Descriptors DEC
- ENERGY TRANSFER; GRAPHITE MODERATED REACTORS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS
Optional Information
- Notes
- For English translation see the journal Soviet Journal of Atomic Energy (USA).