Page 12 - PR 2014 2016 09 Nuclear Reactors and Fuel Cycle

256 Nuclear Reactors and Fuel Cycle | Progress Report

(a) (b) (e)

(c) (d)

Figure 12. Numerical modelling of the plate type fuel for research reactor: a) geometry general view; b) ge-
ometry detail of fuel top section; c) geometry detail of fuel bottom section (nozzle); d) numerical mesh de-
tail of fuel bottom section (nozzle); e) numerical mesh detail of top fuel section.

safety of the IEA-R1 reactor increasing power fuel for research reactors were carried out as
up to 5 MW. Another research project aims to it can be seen in Fig. 12.
design and build a test section for the study
of induced flow in fuel elements of nuclear re- Mechanical Analysis of Nuclear
search reactors parallel plate type vibrations. Research Reactor IEA-R1 Pipelines
The study of the dynamic of the parallel plate
fuel elements behavior is of great importance An engineering project was developed to
to the safety of nuclear research reactors where identify the kind of failure of the decay pipe -
the flow of cooling fluid may reach high op- line, brackets, flanges and screws in chan -
erational conditions (critical speeds) causing nels of the nuclear research reactor IEA-R1
vibrations and may, in the latter case lead to at IPEN-CNEN/SP. The project analysis rec-
the collapse of fuel plates, which can result ommended the work of a consulting firm
in serious accident proportions. Knowledge specialized in corrosion testing with gam-
of the operational limits of the fuel elements magraphy pipe channels of IEA-R1. It was
designed to be used in the research reactor performed a stress analysis simulation of
under development in Brazil requires the test- primary circuit pipeline of IEA-R1 coupled
ing that can be compared with the criteria pipe, props and equipment indicating a
required for your license of operation. In this probable scenario for pipe failure. The after
research project, an experimental test bench failure scenario of the pipeline indicated: a
for fuel elements of nuclear research reactors new project supported channels and chang-
was designed and reconstructed at the Center es in the design of some supporters of the
for Nuclear Engineering (CEN-IPEN-CNEN/ primary circuit. The stress analysis, coupled
SP). The tests consists of analysis of vibration pipe, props and equipment of primary circuit
induced by the flow in the channels formed pipeline of IEA-R1 indicated design modifi-
between the plates and deformation of fuel cations of the media. Technical reports were
plates. Numerical simulations on plate type prepared as part of the announcement to

Instituto de Pesquisas Energéticas e Nucleares