Published April 2013 | Version v1
Report

Spent Fuel Attribute Tester Realization and Application

  • 1. Institute of Isotopes, Hungarian Academy of Sciences, Paks Nuclear Power Plant Ltd., Budapest (Hungary)

Description

Presently 19-element natural uranium fuel bundles are used in 220 MW(e) Indian PHWRs. The core average design discharge burnup for these bundles is 7000 MW.d.Te-1U and maximum burnup for assembly goes upto of 15 000 MW.d.Te-1U. Use of fuel materials like MOX, Thorium, slightly enriched uranium, etc., in place of natural uranium in 19-element fuel bundles, in 220 MW(e) PHWRs is being investigated to achieve higher burnups. The maximum burnup investigated with these bundles is 30 000 MW.d.Te-1U. In PHWR fuel elements no plenum space is available and the cladding is of collapsible type. Studies have been carried out for different fuel element target burnups with different alternative concepts. Modification in pellet shape and pellet parameters are considered. These studies for the PHWR fuel elements/assemblies have been elaborated in this paper. (author)

Part of:
Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting

Additional details

Identifiers

Publishing Information

ISBN
978-92-0-191210-7
Imprint Title
Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
p. 53-58
ISSN
1684-2073
Report number
IAEA-TECDOC-CD--1693

Conference

Title
IAEA-HOTLAB Technical Meeting on Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel
Dates
23-27 May 2011
Place
Smolenice (Slovakia)

Optional Information

Notes
Figs., 2 refs.