Performance characteristics of high Burnup zirlo cladding fuel rods

Guirong Pan, Rose Montgomery, David B. Mitchell

Research output: Contribution to conferencePaperpeer-review

Abstract

Some high burnup (HBU) ZIRLO® cladding fuel rods are being examined at Oak Ridge National Laboratory (ORNL) in support of the Department of Energy's dry storage and transportation research. The rods were provided by Dominion's North Anna Nuclear Power Plant and have a rod-average burnup ranging from 48 to 59 GWd/MTU. Detailed examinations are being conducted in the Oak Ridge National Laboratory hot cell on the high-burnup ZIRLO cladding rods, including rod internal pressure, fission gas composition and release rates, length measurement, eddy current (EC) oxide-thickness measurement, profilometry, visual inspection, metallography, and hot vacuum extraction hydrogen measurements of the cladding. This paper presents some performance characteristics of the ZIRLO clad rods obtained in ORNL to date, including axial growth, in-reactor corrosion, rod internal pressure and fission gas release, and compares them with historical data available. Especially the data will be compared with the pool side and hotcell post irradiation examination (PIE) data from the rods irradiated in the same core in the North Anna plant.

Original languageEnglish
Pages516-522
Number of pages7
StatePublished - 2019
Event17th International High-Level Radioactive Waste Management Conference, IHLRWM 2019 - Knoxville, United States
Duration: Apr 14 2019Apr 18 2019

Conference

Conference17th International High-Level Radioactive Waste Management Conference, IHLRWM 2019
Country/TerritoryUnited States
CityKnoxville
Period04/14/1904/18/19

Funding

The authors extend their gratitude to the utilities that are supporting the spent fuel study program by providing access to their reactors for post irradiation testing and by providing the spent fuel. The authors would also like to acknowledge the efforts of personnel at ORNL and Studsvik Sweden for performing examinations in the hotcell and mechanical test lab.

Keywords

  • Dry storage
  • High burnup
  • Sister rods
  • Used nuclear fuel

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