Published 2004 | Version v1
Book

Developed a spacer grid for the future PWR fuel assembly by considering the thermal/hydraulic and mechanical/structural performance

  • 1. Korea Atomic Energy Research Institute, Yu-sung (Korea, Republic of)

Description

The spacer grid is one of the structural components for the fuel assembly. In order to increase or extend the fuel life cycle, a spacer grid which has a much higher performance from the thermal/hydraulic and mechanical/structural point of view will be needed. From the thermal/hydraulic viewpoint, the CHF (critical heat flux) margin is very important in order to extend its life. Particularly, the mixing flow or cross flow between the subchannels have to be reinforced for this purpose. From the mechanical/structural viewpoint, the critical strength and the fuel rod support behaviour of a spacer grid are the same as the thermohydraulic performance improvement for the next generation fuel. A computational fluid dynamics (CFD) analysis was performed to investigate the coolant mixing in a nuclear fuel bundle that is promoted by the mixing vane on the grid spacer. Single and multiple subchannels of one grid span of the fuel bundle were modeled to simulate a 5*5 rod array experiment with the mixing vane. The three-dimensional CFD models were generated by a structured multi-block method. The standard k-ε turbulence model was used in the current CFD simulation since it is practically useful and converges well for the complex turbulent flow in a nuclear fuel bundle. The CFD predictions of the axial and lateral mean flow velocities showed a somewhat larger difference from the experimental results near the spacer but represented the overall characteristics of the coolant mixing well in a nuclear fuel bundle with the mixing vane. Comparison of the single and multiple subchannel predictions shows a good agreement for the flow characteristics in the central subchannel of the rod array. The simulation of the multiple subchannels shows a slightly off-centered swirl in the peripheral subchannels due to the external wall of the rod array. It also shows no significant swirl and crossflow in the wall subchannels and the corner subchannels. (authors)

Part of:
Proceedings of the 12. international conference on nuclear engineering. Volume 2

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers - ASME
Imprint Place
New York (United States)
ISBN
0-7918-4688-1
Imprint Title
Proceedings of the 12. international conference on nuclear engineering. Volume 2
Imprint Pagination
864 p.
Journal Page Range
p. 223-231

Conference

Title
12. international conference on nuclear engineering - ICONE 12
Dates
25-29 Apr 2004
Place
Arlington - Virginia (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
38060068
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; FLUID FLOW; FUEL ELEMENT CLUSTERS; OPTIMIZATION; PWR TYPE REACTORS; SPACERS
Descriptors DEC
ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 refs.