Page 265 - 00. Complete Version - Progress Report IPEN 2014-2016

Nuclear Reactors and Fuel Cycle | Progress Report 265

Figure 12. Numerical modelling of the plate type fuel for research reactor: a) geometry gener-
al view; b) geometry detail of fuel top section; c) geometry detail of fuel bottom section (nozzle); d) numer-
ical mesh detail of fuel bottom section (nozzle); e) numerical mesh detail of top fuel section.

rious accident proportions. Knowledge of the ulation of primary circuit pipeline of IEA-R1
operational limits of the fuel elements de- coupled pipe, props and equipment indicat-
signed to be used in the research reactor un- ing a probable scenario for pipe failure. The
der development in Brazil requires the test- after failure scenario of the pipeline indicat-
ing that can be compared with the criteria ed: a new project supported channels and
required for your license of operation. In this changes in the design of some supporters of
research project, an experimental test bench the primary circuit. The stress analysis, cou-
for fuel elements of nuclear research reactors
was designed and reconstructed at the Cen-
ter for Nuclear Engineering (CEN-IPEN-CNEN/
SP). The tests consists of analysis of vibration
induced by the flow in the channels formed
between the plates and deformation of fuel
plates. Numerical simulations on plate type
fuel for research reactors were carried out as
it can be seen in Fig. 12.

Mechanical Analysis of Nuclear
Research Reactor IEA-R1 Pipelines

An engineering project was developed to iden-
tify the kind of failure of the decay pipeline,
brackets, flanges and screws in channels of the
nuclear research reactor IEA-R1 at IPEN-CNEN/
SP. The project analysis recommended the work
of a consulting firm specialized in corrosion
testing with gammagraphy pipe channels of
Figure 13. Schematics of the Nuclear Research Reac-
IEA-R1. It was performed a stress analysis sim- tor IEA-R1 primary circuit pipeline and pool.