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

Stefan Nijst; Gert Van den Eynde

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

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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.

Original language	English
Awarding Institution	Hasselt University KU Leuven
Supervisors/Advisors	Malambu Mbala, Edouard, Supervisor Van Iseghem, Pierre, Supervisor Schroeyers, Wouter, Supervisor, External person
Place of Publication	Hasselt, Belgium
Publisher	UHasselt - Universiteit Hasselt
State	Published - 20 Jun 2014

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Improving the radionuclide inventory determination of the Irradiated Graphite from BR1 in MolFinal published version, 4.43 MBLicense: Unspecified

Cite this

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title = "Improving the radionuclide inventory determination of the Irradiated Graphite from BR1 in Mol",

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.",

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N2 - 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.

AB - 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.

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KW - RADIONUCLIDE INVENTORY

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M3 - Master's thesis

PB - UHasselt - Universiteit Hasselt

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