Reflood completion report: Volume 1. A phenomenological thermal-hydraulic model of hot rod bundles experiencing simultaneous bottom and top quenching and an optimization methodology for closure development
Description
In this report, a phenomenological model of simultaneous bottom-up and top-down quenching is developed and discussed. The model was implemented in the TRAC-PF1/MOD2 computer code. Two sets of closure relationships were compared within the study, the Absolute set and the Conditional set. The Absolute set of correlations is frequently viewed as the pure set because the correlations is frequently viewed as the pure set because the correlations utilize their original coefficients as suggested by the developer. The Conditional set is a modified set of correlations with changes to the correlation coefficient only. Results for these two sets indicate quite similar results. This report also summarizes initial results of an effort to investigate nonlinear optimization techniques applied to the closure model development. Results suggest that such techniques can provide advantages for future model development work, but that extensive expertise is required to utilize such techniques (i.e., the model developer must fully understand both the physics of the process being represented and the computational techniques being employed). The computer may then be used to improve the correlation of computational results with experiments
Availability note (English)
Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS DE99001812; NTIS; US GOVT. PRINTING OFFICE DEP.
Files
Additional details
Publishing Information
- Imprint Pagination
- 231 p.
- Report number
- LA-UR--98-3043
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 30036908
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- BLOWDOWN; BURNOUT; CRITICAL HEAT FLUX; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; T CODES; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT FLUX; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-36
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States)