Mechanistic modeling of annular film dryout in annulus geometry in MARS code
Creators
- 1. Dept. of Nuclear Engineering, Seoul National Univ., Seoul (Korea, Republic of)
- 2. TH Safety Research Team, Korea Atomic Energy Research Inst., Daejon (Korea, Republic of)
Description
Annular flow in annulus geometry is characterized as two liquid films flowing along the inner heated rod and outer unheated wall. Critical heat flux (CHF) occurs when the liquid film on the inner heated wall dries out, while there still exists the liquid film on the outer cold wall. In MARS code, the film dryout is calculated by mechanistic model or CHF table look-up method. The mechanistic film dryout is a complex function of film flow rate, applied heat flux and entrainment/deposition rate, etc. and is determined by the hydrodynamic solution. The table look-up method interpolates the AECL-UO CHF table. However, both models were not able to distinguish the liquid films on the cold and hot surfaces in a calculation cell, that is, the cold wall effect. This resulted in over-estimation of the calculated CHF in the single-channel modeling of annulus geometry, which necessitated a new model that could consider the cold wall effect mechanistically in the single-channel modeling. In order to consider the cold wall effect, a mechanistic film splitting model has been developed for the MARS implementation, in which the inner and outer liquid film fractions are solved analytically by introducing a zero shear condition in the vapor core. In addition, the droplet entrainment and deposition models and the transition criterion for annular flow regime have been improved in order to enhance the code accuracy. The new MARS version has been assessed using the KAERI annulus CHF tests and the results showed enhanced agreement with the experimental data. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of NTHAS2: Second Japan-Korea symposium on nuclear thermal hydraulics and safety
- Imprint Pagination
- 800 p.
- Journal Page Range
- p. 777-783
Conference
- Title
- 2. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Acronym
- NTHAS2
- Dates
- 15-18 Oct 2000
- Place
- Fukuoka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32011113
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; ANNULAR SPACE; CRITICAL HEAT FLUX; CYLINDRICAL CONFIGURATION; DRYOUT; EVALUATION; FILMS; M CODES; MATHEMATICAL MODELS; MODIFICATIONS; PWR TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; CONFIGURATION; ENRICHED URANIUM REACTORS; HEAT FLUX; POWER REACTORS; REACTORS; SPACE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs., 11 figs.