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)
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)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44074181
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CLADDING; FUEL ELEMENT CLUSTERS; FUEL ELEMENTS; FUEL PELLETS; MIXED OXIDE FUELS; NATURAL URANIUM; PHWR TYPE REACTORS; SLIGHTLY ENRICHED URANIUM; SPENT FUELS; THORIUM
- Descriptors DEC
- ACTINIDES; DEPOSITION; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; FUEL ASSEMBLIES; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NUCLEAR FUELS; PELLETS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; SURFACE COATING; URANIUM
Optional Information
- Notes
- Figs., 2 refs.