Published 2014 | Version v1
Miscellaneous

Experimental pressure drop and heat transfer in square array rod bundle for fusion-fission hybrid system

  • 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)

Part of:
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association

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.