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Study of the release of the fission gases (Xe and Kr) and the fission products (Cs and I) under anoxic conditions in bicarbonate water

Published online by Cambridge University Press:  13 April 2015

Ernesto González-Robles ,
Markus Fuß ,
Elke Bohnert ,
Nikolaus Müller ,
Michel Herm ,
Volker Metz  and
Bernhard Kienzler
Ernesto González-Robles
Affiliation:
Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany
Markus Fuß
Affiliation:
Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany
Elke Bohnert
Affiliation:
Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany
Nikolaus Müller
Affiliation:
Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany
Michel Herm
Affiliation:
Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany
Volker Metz
Affiliation:
Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany
Bernhard Kienzler
Affiliation:
Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany
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Abstract

For safety assessment analyses of the disposal of spent nuclear fuel (SNF) in deep geological repositories it is indispensable to evaluate the contribution of fission products to the instant release fraction (IRF). During the last three years the EURATOM FP7 Collaborative Project, “Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel (CP FIRST-Nuclides)” was carried out to get a better understanding of the IRF.

Within CP FIRST-Nuclides, a leaching experiment with a cladded SNF pellet was performed in bicarbonate water (19 mM NaCl + 1 mM NaHCO3) under Ar /H2 atmosphere over 333 days. The cladded SNF pellet was obtained from a fuel rod segment which was irradiated in the Gösgen pressurized water reactor; the average burn-up of the segment was 50.4 MWd/kgUO2. In the multi-sampling experiment, gaseous and liquid samples were taken periodically. The moles of the fission gases Kr and Xe released in the gas phase and those of 129I and 137Cs released in solution were measured. Cumulative release fractions of (1.6 ± 0.2)·10-1 fission gases, (1.6 ± 0.1)·10-1129I and (3.9 ± 0.2)·10-2 137Cs, respectively, were achieved after 333 days of leaching. Accordingly the release ratio of fission gases to 129I was 1:1 and the release ratio of fission gases to 137Cs was 4:1, respectively.

Keywords

waste managementCsI
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1744: Symposium EE – Scientific Basis for Nuclear Waste Management XXXVIII , 2015 , pp. 35 - 41
Copyright
Copyright © Materials Research Society 2015 

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