Improving the radionuclide inventory determination of the Irradiated Graphite from BR1 in Mol

Research output: ThesisMaster's thesis

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Abstract

In total, 492 tons of graphite acts as moderator and reflector for the BR1 ( Belgian Reactor 1), located at the site of SCK∙CEN (Studiecentrum voor Kernenergie) in Mol. Radionuclides in the graphite are produced due to nuclear reactions between neutrons and stable nuclies, mainly impurities in the graphite, since the start of the reactor in 1956. The objective of this work was to carry out a numerical simulation of the graphite activation in the BR1 to estimate the radionuclide inventory and specific activity at different locations in the graphite structure. The Monte Carlo burn-up code ALEPH was used for the complex calculation. The fuel configuration changes have been taken into account as well. Together with the current acceptance criteria for surface disposal, published by NIRAS/ONDRAF[1] there was decided which volumes were suited for surface or geological disposal.

Details

Original languageEnglish
Awarding Institution
  • Uhasselt - Hasselt University
  • KUL - Katholieke Universiteit Leuven
Supervisors/Advisors
Place of PublicationHasselt, Belgium
Publisher
  • UHasselt - Universiteit Hasselt
Publication statusPublished - 20 Jun 2014

Keywords

  • BR1, IRRADIATED GRAPHITE, RADIONUCLIDE INVENTORY

ID: 261493