Published 2008 | Version v1
Book

Nuclear data sensitivity studies towards understanding of fuel temperature coefficient in AHWR

  • 1. Bhabha Atomic Research Centre, Mumbai (India)

Description

The Advanced Heavy Water Reactor (AHWR) is a 920 MWth, vertical pressure tube type thorium-based reactor cooled by natural convection by boiling light water and moderated by heavy water. In this paper, we present the isotopic and energy group wise contributions to the Fuel Temperature Coefficient (FTC) in AHWR using our first order perturbation analysis code. In AHWR, the contribution of 239Pu to FTC decreases with burn-up and the contribution of 233U in FTC becomes more negative with burn-up. Also 232Th gives a significant negative contribution, which makes the FTC become more negative with burn-up in AHWR. (authors)

Part of:
Proceedings of the 2007 International Conference on Nuclear Data for Science and Technology - ND 2007

Additional details

Identifiers

Publishing Information

Publisher
EDP Sciences
Imprint Place
Les Ulis (France)
ISBN
978-2-7598-0090-2; 978-2-7598-0091-9
Imprint Title
Proceedings of the 2007 International Conference on Nuclear Data for Science and Technology - ND 2007
Imprint Pagination
1422 p.
Journal Page Range
p. 907-910

Conference

Title
2007 International Conference on Nuclear Data for Science and Technology - ND 2007
Dates
22-27 Apr 2007
Place
Nice (France)

Optional Information

Notes
11 refs.; Full text available on Internet at: http://dx.doi.org/10.1051/ndata:07486