Published May 2001 | Version v1
Miscellaneous Metadata-only

Pressure drop sensitivity analysis of the top nozzle flow plate of PWR fuel assembly

Creators

  • 1. KNFC, Taejon (Korea, Republic of)

Description

A pressure drop sensitivity analysis was performed for the development of top nozzle flow plate of PWR fuel assembly. The three kinds of candidate model were selected for the development of top nozzle flow plate. The analytical models were generated for the 1/8 size of top nozzle plate using the FLUENT code for sensitivity analysis. The analysis range of thickness of flow plate, ligament width and inlet chamfer angle was determined based on the dimensions of the current flow plates of top nozzle in the PWR fuel assembly. The pressure drop characteristics of each candidate model was optimized by performing sensitivity analysis

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[7 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040368
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
F CODES; FUEL ASSEMBLIES; NOZZLES; PRESSURE DROP; PWR TYPE REACTORS; REACTOR CORES; SENSITIVITY ANALYSIS
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 7 figs, 1 tab