Published May 2011 | Version v1
Miscellaneous

Numerical Simulation for a Core Simulator of ACOP

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

An experimental facility, called ACOP, is being constructed in order to evaluate the flow and pressure distribution in the APR+ reactor core. The ACOP facility has a 1/5 linear scale of the prototype. The design is based on the conservation of Euler number which is a ratio of pressure drop to dynamic pressure under a sufficient turbulent flow condition. The each fuel channel in the reactor core, which consists of 257 HIPER fuel assemblies, will be modeled as a 1/5-scale core simulator, which preserves the hydraulic characteristics of the HIPER fuel assembly. The present study is to develop and verify the design parameters applied to the core flow simulator by using a commercial CFD code

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2011 spring meeting of the KNS
Dates
26-27 May 2011
Place
Taebaek (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42099190
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; DESIGN; FUEL ASSEMBLIES; FUEL CHANNELS; PRESSURE DROP; PWR TYPE REACTORS; REACTOR CORES; SIMULATION; TURBULENT FLOW
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref, 4 figs, 2 tabs