Published 2014
| Version v1
Miscellaneous
Experimental pressure drop and heat transfer in square array rod bundle for fusion-fission hybrid system
Creators
- 1. Seoul National Univ., Gwanak Gu, Seoul (Korea, Republic of)
- 2. PhiloSophia Inc., Gwanak Gu, Seoul (Korea, Republic of)
Description
The effects of grid spacer flow restriction on pressure drop are evaluated experimentally for a wide range of flow rates. The results are compared against predictions by using most well known correlations. The convective heat transfer coefficients are evaluated using ANSYS 12.1 for a 3x3 rod bundle for pure water and alumina nanofluid. It is observed that the experimental pressure drop falls within 10%~20% of the predictions. Heat transfer of the 4% alumina nanofluid increases about 18% over pure water under the same inlet flow condition. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-16-2
- Imprint Title
- PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Imprint Pagination
- 270 Megabytes
- Journal Page Range
- [13 p.]
Conference
- Title
- 19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Dates
- 24-28 Aug 2014
- Place
- Vancouver, British Columbia (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 49016384
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FUEL ELEMENT CLUSTERS; HEAT TRANSFER; HYBRID REACTORS; REACTORS; THERMONUCLEAR REACTORS
- Descriptors DEC
- ENERGY TRANSFER; FUEL ASSEMBLIES
Optional Information
- Notes
- Paper PBNC2014-420. 10 refs., 6 tabs., 17 figs.