Published May 2011
| Version v1
Miscellaneous
Numerical Simulation for a Core Simulator of ACOP
Creators
- 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
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