Fuzzy finite element analysis of multi-group neutron diffusion equation with imprecise parameters
by S. Nayak; S. Chakraverty
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 9, No. 1, 2015

Abstract: In this paper, multi-group neutron diffusion equation with imprecise parameters has been solved using proposed fuzzy finite element method. The proposed method is demonstrated by investigating the neutron fluxes viz. thermal and fast group fluxes of a benchmark problem ANL-BSS-6-A2. Various parameters such as thermal conductivity, diffusion, group fission and neutron interaction constants are taken as fuzzy and the uncertain solutions viz. thermal and fast group fluxes are studied in detail. Finally, obtained results are compared with existing ones in special cases and sensitivity of uncertain parameters is analysed.

Online publication date: Thu, 05-Mar-2015

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