A nondiffusive solution method for RETRAN-03 BWR stability analysis
- 1. Computer Simulation and Analysis, Inc., Idaho Falls, ID (United States)
- 2. Electric Power Research Inst., Palo Alto, CA (United States)
Description
Boiling water reactors (BWRs) are susceptible to thermal-hydraulic instabilities which must be considered in their design and operation. Early BWRs were designed to be very stable while operating under natural circulation conditions. As reactor designs have been modified, stability margins have been reduced and the potential for stability events, such as occurred at the La Salle and Vermont Yankee plants, has increased. These events and other considerations point to the need for a reliable analysis tool for predicting the dynamic behavior of these events. This paper presents the development and validation of a conservation equation transport model for the RETRAN-03 time domain thermal-hydraulic analysis code that extends the range of application to simulating the dynamic behavior of stability events. The model has been developed for use with the RETRAN-03 mixture energy and vapor continuity equations that eliminates the numerical diffusion resulting from current models in RETRAN. The transport model has been implemented in RETRAN-03 and results using the five-equation model are presented. Since most time domain thermal-hydraulics systems analysis codes use a donoring approach which makes them susceptible to numerical diffusion, comparisons of the RETRAN-03 solution with the MOC transport model will be made to demonstrate the impact that numerical diffusion can have on stability analyses. Additional RETRAN-03 analyses are presented in the paper that compare simulations of hydrodynamic instability events with data
Additional details
Publishing Information
- Imprint Title
- Seventh international RETRAN conference: Proceedings
- Imprint Pagination
- 650 p.
- Journal Page Range
- p. 4.1-4.22.
- Report number
- EPRI-TR--100361
Conference
- Title
- 7. international RETRAN conference.
- Dates
- 15-18 Sep 1991.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24019555
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BOUNDARY CONDITIONS; BWR TYPE REACTORS; CONVERGENCE; DECAY; DESIGN; DIFFERENTIAL EQUATIONS; HEAT TRANSFER; HYDRAULICS; LA SALLE COUNTY-1 REACTOR; LA SALLE COUNTY-2 REACTOR; LOSS OF COOLANT; NATURAL CONVECTION; R CODES; REACTIVITY; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; REACTOR STABILITY; SENSITIVITY; SUBCOOLING; TIME DEPENDENCE; TWO-PHASE FLOW; VERIFICATION; VERMONT YANKEE REACTOR; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONVECTION; COOLING; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID FLOW; OPERATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; STABILITY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9109388--.