According to the literature survey, several scaling studies have been performed to derive a set of scaling criteria which were thought to be suitable for reproducing the major thermal-hydraulic phenomena in a scaled-down CANDU moderator tank similar to that in a prototype power plant during a full power steady state condition [1,2,3]. The objective of building this scaled-down moderator tank is to generate the experimental data necessary to validate the computer codes which are used to analyze the accident analysis of CANDU-6 plants. The major variables of interests in this paper are moderator flow velocity and temperature of the moderator which is D2O inside the moderator tank during a steady state and transient conditions. The reason is that the local subcooling of the moderator is found to be a critical parameter determining whether the stable film boiling can sustain on the outer surface of the calandria tube if the contact of overheated pressure tube and cold calandria tube should occur due to pressure tube ballooning during LBLOCA with ECC injection failure. The key phenomena involved include the inlet jet development and impingement, buoyancy force driven by the moderator temperature gradient caused by non-uniform direct heating of the moderator, and the pressure drop due to viscous friction of the flow across the calandria tube array. In this paper, the previous researches are reviewed, some concerns or potential problems associated with them implied by comparing CFD analyses results between the CANDU-6 moderator tank and 1/4 scaled-down test facility are described, and as a way to examine the assumption of the scaling analysis is true an order-of-magnitude analyses are performed. Based on the results of these analyses the assumption of neglecting (∇*)2V* .and (∇*)2T* terms cannot be justified for the power of 0.5 MW and 1.566 MW for the 1/4 scaled-down facility. Further investigation is thought to be necessary to confirm this result, i.e. if the scaling of the previous work1 is justifiable by some other independent analyses.
Reconsideration of a Scaling Study of CANDU-6 Moderator Tank Scaled-Down Test Facility
- Views Icon Views
- Share Icon Share
- Search Site
Rhee, BW, Kim, HT, & Song, YM. "Reconsideration of a Scaling Study of CANDU-6 Moderator Tank Scaled-Down Test Facility." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 2A: Thermal Hydraulics. Prague, Czech Republic. July 7–11, 2014. V02AT09A042. ASME. https://doi.org/10.1115/ICONE22-30315
Download citation file: