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Similar Items: Fuel chemistry and pellet-clad interaction related to high burnup fuel.

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Advances in fuel pellet technology for improved performance at high burnup.
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A study on friction and axial effects in PELLET-CLAD mechanical interaction
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Influence of water chemistry on fuel cladding behaviour: proceedings.
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A model of fuel pellet swelling and its relation with grain growth
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Fuel cladding interaction with water coolant in power reactors: A survey report of a co-ordinated research programme on the investigation of fuel element cladding interaction with water coolant in power reactors.
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Determination of research reactor fuel burnup.
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Nuclear fuel behaviour modelling at high burnup and its experimental support.
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Technical and economic limits to fuel burnup extension.
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Impact of extended burnup on the nuclear fuel cycle.
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Water reactor fuel element modelling at high burnup and its experimental support.
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Influence of graphite discs, chamfers, and plenums on temperature distributions in high burnup fuel.
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Fuel performance at high burnup for water reactors: proceedings of a technical committee meeting.
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Fuel modelling at extended burnup: FUMEX 1993-1996.
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Implementation of burnup credit in spent fuel management systems.
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Implementation of burnup credit in spent fuel management systems.
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Iodine induced stress corrosion cracking of Zircaloy fuel cladding materials.
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Analysis and modelling of the chemical interactions between inconel grid spacers and zircaloy cladding of LWR fuel rods; formation of liquid phases due to chemical interactions.
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Performance of Bruce natural UO2 fuel irradiated to extended burnups.
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Extended-burnup CANDU fuel: description of database and comparisons with code predictions.
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Standard specification for wrought zirconium alloy seamless tubes for nuclear reactor fuel cladding.
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Water chemistry and corrosion control of cladding and primary circuit components.
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Integrity: A Semi-mechanistic model for stress corrosion cracking of fuel: IAEA Technical Committee Meeting on water reactor fuel element modelling at high burnup and its experimental support.
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Long-term safety of radioactive waste disposal: reaction of high burnup spent fuel and UO2 in saline brines at room temperature.
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Behaviour of Bruce NGS-A fuel irradiated to a burnup of ~500 MWh/kgU.

Author: Technical committee meeting on fuel chemistry and pellet-clad interaction related to high burnup fuel Nykoping,SE

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Fuel chemistry and pellet-clad interaction related to high burnup fuel.