Published 2019 | Version v1
Book

RMB experimental program on the hydrodynamical behavior of fuel assemblies

  • 1. Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)
  • 2. Reator Multipropósito Brasileiro (RMB), São Paulo, SP (Brazil)

Description

The Brazilian Multipurpose Reactor - RMB is a 30 MW pool type research reactor, that uses Materials Testing Reactor - MTR type fuel assemblies. It has a 5x5 square array core with 23 fuel assemblies and two in-core irradiation positions, operating with upward flow and average velocities nearly 10 m/s in the fuel plates channels. The IEA-R1 is a 5 MW pool type research reactor, which also has a 5x5 square array core with 19 standard fuel assemblies, four control fuel assemblies and a central beryllium irradiation device. It operates with downward flow nearly 1.8 m/s in the channels. In order to verify and provide data and information about the dynamical behavior of fuel assemblies under nominal and critical conditions, the experimental circuit ORQUÍDEA is being designed. This information will be very important for the licensing process of the fuel assembly before its use in the reactor core. This circuit will permits upward and downward flow and dynamical behavior of the fuel assemblies and its parts will be tested and verified. Flow rate, temperature, pressure and differential pressure transducers are the instruments of the circuit. Endurance and critical flow velocity tests will be performed. Dummy fuel assemblies will be used in the tests. It will be instrumented with pressure, strain-gages and flow velocity instruments. The COLIBRI experimental circuit is being designed to make tests that allow the studies of the fluid-structure phenomenology of fuel plates similar to those of the RMB fuel assemblies when subjected to high flow velocities, which can induce pressure differences between the channels formed by the fuel plates. Preliminary structural response studies of the plate's behavior were performed using a Finite Element Analysis model generated by ANSYS Mechanical. The pressure loadings caused by the fluid flow were calculated using a Computational Fluid Dynamics model created with ANSYS CFX. The fluid-structure interactions will be verified for different channel configurations. In this circuit, vibrations and collapse of the dummy fuel plates will be tested. Experimental data will be compared with CFD (Computational Fluid Dynamics) calculations. This work presents a preliminary design for the ORQUÍDEA and COLIBRI experimental circuits to be built at the Instituto de Pesquisas Energéticas e Nucleares - IPEN of the Comissão Nacional de Energia Nuclear - CNEN. (author)

Part of:
Proceedings of the INAC 2019: international nuclear atlantic conference. Nuclear new horizons: fueling our future

Additional details

Publishing Information

Publisher
ABEN
Imprint Place
Rio de Janeiro, RJ (Brazil)
ISBN
978-85-99141-08-3
Imprint Title
Proceedings of the INAC 2019: international nuclear atlantic conference. Nuclear new horizons: fueling our future
Imprint Pagination
6019 p.
Journal Page Range
p. 4440-4449

Conference

Title
international nuclear atlantic conference; 21. meeting on nuclear reactor physics and thermal hydraulics - ENFIR; 14. meeting on nuclear applications - ENAN; 6. meeting on nuclear industry - ENIN; 1. international workshop on thorium - ITHOR-WS
Acronym
INAC 2019
Dates
21-25 Oct 2019
Place
Santos, SP (Brazil)

Optional Information

Notes
R02-043