Comprehensive scale model for LMFBR reactor assembly thermal hydraulics. (7th February 2008)

• Record Type: Journal Article
• Authors: Padmakumar, G.; Prakash, V.; Banerjee, I.; Thirumalai, M.; Babu, C.; Prabhakar, R.; Vaidyanathan, G.
• Is Part Of: International journal of nuclear energy, science and technology. Volume 3:Number 4(2007)
• Page Start: 325
• Page End: 344
• Publication Date: 2008-02-07
• Subjects: 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; Nuclear energy -- Periodicals; 621.4805
• Languages: English
• ISSNs: 1741-6361

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.