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Related Experiment Video

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Laser-heating and Radiance Spectrometry for the Study of Nuclear Materials in Conditions Simulating a Nuclear Power Plant Accident
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Radiological characterisation of graphite components in Advanced Gas-cooled Reactor cores.

A Tzelepi1, M P Metcalfe1, J H Dinsdale-Potter1

  • 1National Nuclear Laboratory, Fuels, Reactors and Reprocessing, Central Laboratory, Sellafield, CA20 1PG, United Kingdom.

Journal of Environmental Radioactivity
|June 21, 2020
PubMed
Summary
This summary is machine-generated.

This study characterizes carbon-14 (C-14) in Advanced Gas-cooled Reactor (AGR) graphite, providing crucial data for decommissioning. Findings suggest alternative, cost-effective storage and disposal options for graphite fuel sleeves.

Keywords:
C-14DecommissioningGilsocarbonH-3Thermal treatment

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Area of Science:

  • Nuclear Engineering
  • Radiochemistry
  • Materials Science

Background:

  • Advanced Gas-cooled Reactors (AGR) are nearing the end of their operational life.
  • Decommissioning strategies require accurate radiological characterization of components.
  • Existing radiological data for AGR graphite is limited, necessitating new research.

Purpose of the Study:

  • To quantify carbon-14 (C-14) activity and understand its release behavior in AGR core graphite and associated deposits.
  • To provide radiological data (C-14, H-3, gamma spectrometry) for AGR graphite fuel sleeves.
  • To inform decommissioning strategies and evaluate waste management options for AGR components.

Main Methods:

  • Radiological analysis of AGR core graphite and carbonaceous deposits.
  • Measurement of C-14 and H-3 activity using gamma spectrometry.
  • Characterization of graphite fuel sleeves.

Main Results:

  • This is the first study to report C-14 activity and release behavior in AGR core graphite and deposits.
  • Significant understanding of C-14 precursors in both AGR and Magnox graphite and deposits was achieved.
  • Radiometric data for AGR graphite fuel sleeves were obtained, highlighting a costly waste stream.

Conclusions:

  • The study provides essential radiological data to support AGR decommissioning.
  • Findings on C-14 in graphite and deposits enhance understanding of radionuclide behavior.
  • Alternative, lower-impact storage and disposal options for AGR graphite fuel sleeves should be considered.