Experimental investigation of flow-induced vibration in PFBR steam generator sector model
by M. Thirumalai, V. Prakash, R. Srinivasan, C. Anand Babu, R. Prabhakar, G. Vaidyanathan
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 3, No. 1, 2007

Abstract: The 500 MWe Prototype Fast Breeder Reactor (PFBR) is under construction at Kalpakkam. It is a liquid metal sodium-cooled pool-type fast reactor with all primary components located inside a sodium pool. Fission heat is transferred to a secondary sodium system in an intermediate heat exchanger, which is in turn transferred to water in a Steam Generator (SG). The PFBR-SG is a vertical shell and tube-type heat exchanger with sodium in its shell side and water in the tube side. Flow-Induced Vibration (FIV) experiments were carried out in a water test loop on a 60-degree sector model to validate the design and also to qualify the component for plant operation.

Online publication date: Tue, 13-Feb-2007

The full text of this article is only available to individual subscribers or to users at subscribing institutions.

 
Existing subscribers:
Go to Inderscience Online Journals to access the Full Text of this article.

Pay per view:
If you are not a subscriber and you just want to read the full contents of this article, buy online access here.

Complimentary Subscribers, Editors or Members of the Editorial Board of the International Journal of Nuclear Energy Science and Technology (IJNEST):
Login with your Inderscience username and password:

Username:        Password:          Forgotten your password?

Want to subscribe?
A subscription gives you complete access to all articles in the current issue, as well as to all articles in the previous three years (where applicable). See our Orders page to subscribe.

If you still need assistance, please email subs@inderscience.com