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

Research output: ThesisMaster's thesis

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Improving the radionuclide inventory determination of the Irradiated Graphite from BR1 in Mol. / Nijst, Stefan; Van den Eynde, Gert (Peer reviewer).

Hasselt, Belgium : UHasselt - Universiteit Hasselt, 2014. 96 p.

Research output: ThesisMaster's thesis

Bibtex - Download

@phdthesis{6b6e73643b304e67af90c439557c7d7b,
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.",
keywords = "BR1, IRRADIATED GRAPHITE, RADIONUCLIDE INVENTORY",
author = "Stefan Nijst and {Van den Eynde}, Gert",
note = "Score = 2",
year = "2014",
month = "6",
day = "20",
language = "English",
publisher = "UHasselt - Universiteit Hasselt",
school = "Uhasselt - Hasselt University , KUL - Katholieke Universiteit Leuven",

}

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TY - THES

T1 - Improving the radionuclide inventory determination of the Irradiated Graphite from BR1 in Mol

AU - Nijst, Stefan

A2 - Van den Eynde, Gert

N1 - Score = 2

PY - 2014/6/20

Y1 - 2014/6/20

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.

KW - BR1

KW - IRRADIATED GRAPHITE

KW - RADIONUCLIDE INVENTORY

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_137279

M3 - Master's thesis

PB - UHasselt - Universiteit Hasselt

CY - Hasselt, Belgium

ER -

ID: 261493