Abstract The core inlet flow rates and exit pressure distributions of an APR+ (Advanced Power Reactor Plus) reactor were evaluated experimentally with the ACOP (APR+ Core Flow & Pressure) test facility. The ACOP test facility was constructed with a linear reduced scale of 1/5 referring to the APR+ reactor. The major flow path from the clod leg to hot leg was preserved with a principle of similarity. The core region was simulated using 257 core simulators, which are representative of the real HIPER fuel assemblies that APR+ reactor adopted. The core inlet flow rates and pressure distributions along the main flow path, which are significant information as an input data to evaluate the core thermal margin and reactor safety, were obtained by differential pressures measured at core simulators representing 257 fuel assemblies, and the static or differential pressures at 584 points, respectively. Two kinds of experiments, 4-pump balanced and unbalanced flow conditions, were conducted to examine the hydraulic characteristics of the reactor coolant flow. The mass balance and overall pressure drop were carefully examined to check the reliability of the obtained values. The inlet flow rates of the two test results showed similar distributions, which met the hydraulic performance requirement. The details of these experiments, the facility, and a data analysis are also described in this paper.
[1]
B. Lee,et al.
A Review on the Regionalization Methodology for Core Inlet Flow Distribution Map
,
2001
.
[3]
Ki-Hwan Kim,et al.
A FLOW AND PRESSURE DISTRIBUTION OF APR+ REACTOR UNDER THE 4-PUMP RUNNING CONDITIONS WITH A BALANCED FLOW RATE
,
2012
.
[4]
D. J. Euh,et al.
Hydraulic characteristics of smart reactor for a nominal condition
,
2012
.
[5]
M. Böttcher,et al.
Detailed CFX-5 study of the coolant mixing within the reactor pressure vessel of a VVER-1000 reactor during a non-symmetrical heat-up test
,
2008
.
[6]
G. Hetsroni.
Use of Hydraulic Models in Nuclear Reactor Design
,
1967
.
[7]
Kun Yuan,et al.
CFD analysis of PWR core top and reactor vessel upper plenum internal subdomain models
,
2011
.