Published February 2019 | Version v1
Journal article

Numerical simulation of complex hexagonal structures to predict drop behavior under submerged and fluid flow conditions

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
  • 2. ELSOLTEC Inc., Yongin (Korea, Republic of)

Description

This study simulated a control rod assembly (CRA), which is a part of reactor shutdown systems, in immersed and fluid flow conditions. The CRA was inserted into the reactor core within a predetermined time limit under normal and abnormal operating conditions, and the CRA (which consists of complex geometric shapes) drop behavior is numerically modeled for simulation. A full-scale prototype CRA drop test is established under room temperature and water-fluid conditions for verification and validation. This paper describes the details of the numerical modeling and analysis results of the several conditions. Results from the developed numerical simulation code are compared with the test results to verify the numerical model and developed computer code. The developed code is in very good agreement with the test results and this numerical analysis model and method may replace the experimental and CFD method to predict the drop behavior of CRA

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
51
Journal Issue
1
Series
13 refs, 10 figs, 8 tabs
Journal Page Range
p. 31-44
ISSN
1738-5733

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50048014
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
COMPUTERIZED SIMULATION; CONTROL ELEMENTS; FLUID FLOW; FLUID MECHANICS; NUMERICAL ANALYSIS; REACTOR CORES; REACTOR SHUTDOWN; VERIFICATION
Descriptors DEC
MATHEMATICS; MECHANICS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; SHUTDOWN; SIMULATION