Title: Comprehensive scale model for LMFBR reactor assembly thermal hydraulics

Authors: G. Padmakumar, V. Prakash, I. Banerjee, M. Thirumalai, C. Anand Babu, R. Prabhakar, G. Vaidyanathan

Addresses: Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India. ' Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India. ' Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India. ' Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India. ' Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India. ' Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India. ' Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India

Abstract: The construction of the 500 MWe Prototype Fast Breeder Reactor (PFBR) is underway at Kalpakkam, India. This liquid sodium-cooled reactor is a pool-type reactor with two secondary loops. Experimental investigations have been carried out to understand the complex flow, temperature patterns and flow-induced vibration characteristics. To enhance the confidence in the design of the components immersed in the pool of the reactor and to reduce the scale effects, a large scale model was constructed. The Scale Model for Reactor Thermal Hydraulics (SAMRAT) is a one-by-four scaled-down model of the reactor assembly of PFBR. This model is a unique one in that it attempts to investigate multiple phenomena using a single model. This paper describes the details of the model – the scaling criteria adopted, the simulation for each study, and the methodology of the study and the salient features of the model – and examines the results.

Keywords: fast breeder reactors; FBR; similarity; thermal hydraulics; modelling laws; liquid sodium-cooled reactors; India; temperature patterns; flow-induced vibration; scale models; reactor assembly; simulation; nuclear technology; nuclear energy; nuclear power.

DOI: 10.1504/IJNEST.2007.017074

International Journal of Nuclear Energy Science and Technology, 2007 Vol.3 No.4, pp.325 - 344

Published online: 06 Feb 2008 *

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