Critical Velocity Experimental Assessment in Flat Plate Fuel Element for Nuclear Research Reactor

Authors

DOI:

https://doi.org/10.15392/bjrs.v10i3.2051

Keywords:

Critical velocity, plate fuel element, channel blockage, nuclear reactor

Abstract

Aluminum-coated plates, containing a uranium silicide (U3Si2) meat dispersed in an aluminum matrix, are commonly used in the fuel elements of Material Testing Reactors (MTRs).  These fuel elements are typically comprised of narrow channels formed by parallel flat plates, which allow coolant flow to remove the heat of fission reactions. It is important to mention that the thickness of the plates is much smaller than their width and height. The high flow rates needed to ensure efficient fuel-element cooling may cause fuel-plate mechanical failures due to instability induced by the flow in the channels. In the case of critical velocity, excessive permanent deflections of these plates can cause blockage of the flow channels and lead to overheating.  An experimental facility that simulates a plate-like fuel element with three coolant channels was developed for this work. The test-section dimensions were based on the Fuel Element design of the Brazilian Multipurpose Reactor (RMB), project being coordinated by the National Commission of Nuclear Energy (CNEN). Experiments were performed to reach Miller's critical velocity condition. This critical condition was reached at 14.5 m/s leading to consequent plastic deformation of the fuel plates

Downloads

Download data is not yet available.

References

. W. M. TORRES et. al., “A MTR Fuel Element Flow Distribution Measurement Pleminary Results,” (2003); https://www.rertr.anl.gov/RERTR25/HTML/Torres.html

. A. J. A. CASTRO and D. A. ANDRADE, “Experimental Investigation Of Critical Velocity In Fuel Element For The RMB Reactor”, presented at 17th Brazilian Congress of Thermal Sciences and Engineering, Águas de Lindóia, SP, Brazil November 25-28, (2018);

. D. R. MILLER, “Critical Flow Velocities for Collapse of Reactor Parallel-Plate Fuel Assemblies,” J. Eng. Power, 82(2):83-91, (1960); https://doi.org/10.1115/1.3672746 DOI: https://doi.org/10.1115/1.3672746

. A. J. A. Castro, “Experimental Analysis of Critical Velocity in Flat Plate Fuel Element for Nuclear Research Reactors,” Ph.D. thesis, IPEN, Univ. São Paulo, São Paulo, Brazil 2017 (in Portuguese)

. R. D. GRONINGER and J. J. KANE, “Flow induced deflections of parallel flat plates,” Nuclear Engineering and Design, 16:218-226, (1963); https://doi.org/10.13182/NSE63-A26503 DOI: https://doi.org/10.13182/NSE63-A26503

. R. SCAVUZZO, “Hydraulic Instability of Flat Parallel-Plate Assemblies,” Nuclear Engineering and Design, 21:463-472 (1965); https://doi.org/10.13182/NSE65-A18790 DOI: https://doi.org/10.13182/NSE65-A18790

. G. SMISSAERT, “Static and Dynamic Hydroelastic Instabilities in MTR-Type Fuel Elements Part I. Introduction and Experimental Investigation,” 7(6):535-546 (1968); https://doi.org/10.1016/0029-5493(68)90103-9 DOI: https://doi.org/10.1016/0029-5493(68)90103-9

. M. HO, G. HONG and A. N. F. MACK, “Experimental Investigation of Flow-Induced Vibration In a Parallel Plate Reactor Fuel Assembly,” presented at the 15th Australian Fluid Mechanics Conference, Sydney, Australia, Dec. 13-17, 2004.

. IAEA, “Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels Guidebook,” IAEA Physics Section, Vienna, Austria, IAEA-TECDOC-233, Aug. 1988.

. G. KIM and D. C. DAVIS, “Hydraulic instabilities in flat-plate type fuel assemblies,” Nuclear Engineering and Design, 158(1):1-17 (1995); https://doi.org/10.1016/0029-5493(95)01023-B DOI: https://doi.org/10.1016/0029-5493(95)01023-B

. J. E. R. SILVA, “Concepção do elemento combustível do RMB,” IPEN, Brazil, RMB-10300-002-00, Fev. 2011 (in Portuguese)

. J. E. R. SILVA, “Descrição do projeto de concepção do núcleo, componentes, estruturas e instalações associadas ao núcleo do Reator Multipropósito Brasileiro- RMB, IPEN, Brazil, RMB-N01-00-PC-10300-RD-006-Revisão 0B, Aug. 2013 (in Portuguese)

. C. A. OLIVEIRA and and M. MATTAR NETO, “Flow velocity calculation to avoid instability in a Typical Research Reactor Core,” presented at International Nuclear Atlantic Conference, Belo Horizonet, Brazil, 2011.[Online] Available: https://inis.iaea.org/search/search.aspx?orig_q=RN:43050775 Accessed on: Jan. 17, 2022.

. P. JENSEN and W. R. MARCUM, “Predicting critical flow velocity leading to laminate plate collapse- flat plates,” Nuclear Engineering and Design, 267:71-87 (2014); https://doi.org/10.1016/j.nucengdes.2013.11.071 DOI: https://doi.org/10.1016/j.nucengdes.2013.11.071

. J. G. MANTECÓN and M. MATTAR NETO, “Numerical methodology for fluid-structure interaction analysis of nuclear fuel plates under axial flow conditions,” Nuclear Engineering and Design, 333:78-86 (2018); https://doi.org/10.1016/j.nucengdes.2018.04.009 DOI: https://doi.org/10.1016/j.nucengdes.2018.04.009

. J. G. MANTECÓN and M. MATTAR NETO, “Numerical investigation on the effects of geometric deviations and materialsproperties on flow-induced deflections of fuel plates,” Annals of Nuclear Energy, 140: 107118( 2020); https://doi.org/10.1016/j.anucene.2019.107118. DOI: https://doi.org/10.1016/j.anucene.2019.107118

Downloads

Published

2022-09-18

How to Cite

Andrade, D. A., Gonzalez Mantecón, J., Navarro de Mesquita, R., Mattar Neto, M., Ernesto Umbehaun, P., & Maximo Torres, W. (2022). Critical Velocity Experimental Assessment in Flat Plate Fuel Element for Nuclear Research Reactor. Brazilian Journal of Radiation Sciences, 10(3). https://doi.org/10.15392/bjrs.v10i3.2051

Issue

Section

Articles

Most read articles by the same author(s)