An assessment of TRAC-PD2 refill calculations based on Creare countercurrent flow tests
Creators
- 1. Los Alamos National Laboratory, Energy Division P.O. Box 1663, MS 553, Los Alamos, New Mexico 87545
Description
An important step in computer code development is the assessment of code capabilities through comparison of calculated results with experimental data A number of Creare countercurrent flow tests were simulated with the Transient Reactor Analysis Code (TRAC)-PD2 code to assess the emergency core coolant (ECC) lower plenum penetration and refill predictive capabilities. The tests examined in this study indicate a prediction of complete bypass and delivery at countercurrent steam flows where these phenomena occurred experimentally. Steam flows leading to partial delivery experimentally did not always lead to partial delivery in the calculations, however. A number of parameters can potentially effect TRAC refill calculations. Sensitivity studies indicate the TRAC results are most sensitive to droplet Weber number variations that affect interfacial shear and heat transfer rates. The condensation model also affects calculations with subcooled ECC liquid
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 57
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- 134-139
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16003057
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; COOLANTS; COUNTER CURRENT; ECCS; FLOW MODELS; FLUID MECHANICS; FLUID-STRUCTURE INTERACTIONS; HEAT TRANSFER; HYDRAULICS; INTERFACES; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR CORES; REACTOR SIMULATORS; SENSITIVITY ANALYSIS; SHEAR; STEAM; SUBCOOLING; SURFACE TENSION; SYSTEMS ANALYSIS; T CODES; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; COMPUTER CODES; COOLING; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; MATHEMATICAL MODELS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; SIMULATORS; SURFACE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS