In-reactor performance of prototype SBR MOX fuel
Creators
- 1. BNFL International Group, British Nuclear Fuels Plc, Sellafield, Seascale, Cumbria (United Kingdom)
- 2. LWR Business Unit, British Nuclear Fuels Plc, Springfields (United Kingdom)
Description
As part of the international Callisto experiment, BNFL have undertaken the base irradiation, ramp testing and post-irradiation examination of two fuel rods, manufactured by BNFL's Short Binderless Route (SBR) for MOX fuel. Although of only short (lm) length, the rods were in other respects of standard PWR geometry. Base irradiation was performed in the Callisto loop of the BR2 reactor and achieved burn-ups of 17 GWd/tM, 28 GWd/tM peak pellet, at moderate to high power levels. No problems were encountered during base irradiation, confirmed by intermediate examination. In a separate BR2 capsule, a ramp test was then performed on one of the two rods. Again, the rod showed no problems and was discharged intact. The ramp test conditions employed were somewhat more onerous than the level corresponding to the best-estimate failure level for standard UO2 fuel. The survival of the rod confirms the general observation that the PCI failure resistance of MOX fuel is superior to that of standard UO2. The irradiation has been followed by a detailed programme of non-destructive and destructive hot-cell examinations on both of the rods. Profilometry, ECT and gamma-scanning confirmed the overall satisfactory performance of the rods and the absence of incipient damage. Puncture testing and gas analysis showed the fission gas release levels in both the ramped and unramped rods to be in line with what would be expected for a UO2 rod. The satisfactory microstructure of the fuel was confirmed via optical ceramography and autoradiography. This paper will describe the fuel manufacture, base irradiation and ramp test conditions, and will provide a summary of the results of the PIE programme. (author)
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29054766.pdf
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Additional details
Publishing Information
- Imprint Title
- Advances in fuel pellet technology for improved performance at high burnup. Proceedings of a Technical Committee meeting
- Imprint Pagination
- 425 p.
- Journal Page Range
- p. 399-408
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1036
Conference
- Title
- Technical Committee meeting on advances in fuel pellet technology for improved performance at high burnup
- Dates
- 28 Oct - 1 Nov 1996
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 29054766
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BNFL; BR-2 REACTOR; DESTRUCTIVE TESTING; FAILURES; FUEL FABRICATION PLANTS; GAMMA FUEL SCANNING; MIXED OXIDE FUELS; NONDESTRUCTIVE TESTING; POST-IRRADIATION EXAMINATION; TOMOGRAPHY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL SCANNING; FUELS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING; MATERIALS TESTING REACTORS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; UNITED KINGDOM ORGANIZATIONS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs, 1 tab