A parametric study of variables affecting BWR instability
Creators
- 1. Idaho National Engineering Laboratory, EG and G Idaho, Inc., Idaho Falls, Idaho (United States)
Description
Calculations were performed to investigate the effect of ranging several key variables on the power response of a BWR core subjected to periodic flow oscillations, such as those that might be exhibited during an instability event. It was observed that flow oscillation amplitude, its frequency, and core inlet flow subcooling have the greatest impact on the magnitude of resultant power oscillations. In particular, when flow is oscillated at a frequency of about 0.235 Hz for a typical 8 X 8 BWR rod bundle, it may produce power peaks more than 100 times the initial power. Further, based on some experimental data and supporting calculations, it is shown that increasing feedwater subcooling leads to both increased flow amplitude and decreasing frequency in a boiling natural circulation loop. It was concluded that the degree of subcooling of feedwater is the single most important parameter affecting the magnitude of reactor power oscillations. In summary: A single channel TRAC -BF1 model of a BWR core to study the effect of individual parameter variations, on reactor peak and average power during flow oscillations. These included flow amplitude, flow oscillation frequency, inlet subcooling, gap conductance, number of parallel channels and several others. In addition, the effects of temporal and spatial discretization of the problem were assessed. Among these, the inlet flow conditions have the strongest effect on the magnitude of power oscillations. In particular, the power peaks are very sensitive to the frequency of the flow oscillation and there is a critical frequency of the flow oscillation that produces very high peaks in the power. In the second part of this study it was shown that reduction of the feedwater temperature in a natural circulation boiling system reduces the flow oscillation frequency and increases its amplitude. It is concluded that in a BWR, during natural circulation, it is critical to maintain feedwater temperature control to prevent high subcooling of the core synergism of three separate effects, namely: higher moderation, increased amplitude and decreased frequency of the flow oscillations. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the International Workshop on Boiling Water Reactor Stability
- Imprint Pagination
- 561 p.
- Journal Page Range
- p. 269-282
- Report number
- NEA-CSNI-R--1990-178
Conference
- Title
- International Workshop on Boiling Water Reactor Stability
- Dates
- 17-19 Oct 1990
- Place
- Holtsville, New York (United States)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39093645
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMPLITUDES; BOILING; BWR TYPE REACTORS; CRITICAL FREQUENCY; FEEDWATER; FUEL ELEMENT CLUSTERS; INSTABILITY; NATURAL CONVECTION; OSCILLATIONS; PARAMETRIC ANALYSIS; SUBCOOLING; TEMPERATURE CONTROL
- Descriptors DEC
- CONTROL; CONVECTION; COOLING; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT TRANSFER; HYDROGEN COMPOUNDS; MASS TRANSFER; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs.