Thermal-hydraulic and characteristic models for packed debris beds
Description
APRIL is a mechanistic core-wide meltdown and debris relocation computer code for Boiling Water Reactor (BWR) severe accident analyses. The capabilities of the code continue to be increased by the improvement of existing models. This report contains information on theory and models for degraded core packed debris beds. The models, when incorporated into APRIL, will provide new and improved capabilities in predicting BWR debris bed coolability characteristics. These models will allow for a more mechanistic treatment in calculating temperatures in the fluid and solid phases in the debris bed, in determining debris bed dryout, debris bed quenching from either top-flooding or bottom-flooding, single and two-phase pressure drops across the debris bed, debris bed porosity, and in finding the minimum fluidization mass velocity. The inclusion of these models in a debris bed computer module will permit a more accurate prediction of the coolability characteristics of the debris bed and therefore reduce some of the uncertainties in assessing the severe accident characteristics for BWR application. Some of the debris bed theoretical models have been used to develop a FORTRAN 77 subroutine module called DEBRIS. DEBRIS is a driver program that calls other subroutines to analyze the thermal characteristics of a packed debris bed. Fortran 77 listings of each subroutine are provided in the appendix
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A06/MF A01 - GPO as TI87003500.
Files
Additional details
Publishing Information
- Imprint Pagination
- 105 p.
- Report number
- NUREG/CR--4689
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18065785
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; BWR TYPE REACTORS; CORIUM; FLUID FLOW; FORTRAN; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; MELTDOWN; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PROGRAMMING LANGUAGES; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- ORNL/TM--10117.