% IMPORTANT: The following is UTF-8 encoded. This means that in the presence
% of non-ASCII characters, it will not work with BibTeX 0.99 or older.
% Instead, you should use an up-to-date BibTeX implementation like “bibtex8” or
% “biber”.
@BOOK{Chiriki:136200,
author = {Chiriki, Suresh},
title = {{D}isposal strategy of proton irradiated mercury from high
power spallation sources},
volume = {67},
school = {RWTH Aachen},
type = {Dr.},
address = {Jülich},
publisher = {Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag},
reportid = {PreJuSER-136200},
isbn = {978-3-89336-632-3},
series = {Schriften des Forschungszentrums Jülich. Reihe Energie und
Umwelt / Energy und Environment},
pages = {XIV, 124 S.},
year = {2010},
note = {Record converted from JUWEL: 18.07.2013; RWTH Aachen,
Diss., 2010},
abstract = {Large spallation sources are intended to be constructed in
Europe (EURISOL: nuclear physics research facility and ESS:
European Spallation Source). These facilities would
accumulate more than 20 metric tons of irradiated mercury in
the target, which has to be treated as highly radioactive
and chemo-toxic waste. Liquid waste cannot be tolerated in
European repositories. As part of this work on
safety/decommissioning of high-power spallation sources, our
investigations were focused mainly to study experimentally
and theoretically the solidification of liquid mercury waste
(selection of an adequate solid mercury form and of an
immobilization matrix, chemical engineering process studies
on solidification/stabilization and on encapsulating in a
matrix). Based on experimental results and supported by
literature Hg-chalcogens (HgS, HgSe) will be more stable in
repositories than amalgams. Our irradiation experimental
studies on mercury waste revealed that mercury sulfide is a
reasonable solid for disposal and shows larger stability in
possible accidents with water ingress in a repository.
Additionally immobilization of mercury in a cement matrix
and polysiloxane matrix were tested. HgS formation from
liquid target mercury by a wet process is identified as a
suitable formation procedure. These investigations reveal
that an almost $99.9\%$ elementary Hg conversion can be
achieved and that wet process can be reasonably handled
under hot cell conditions.},
cin = {IEF-6},
ddc = {500},
cid = {I:(DE-Juel1)VDB814},
shelfmark = {UXV - Radioactive waste disposal - interim and final / UXV
- Entsorgung von radioaktiven Abfällen (Zwischen- und
Endlagerung)},
typ = {PUB:(DE-HGF)3},
url = {https://juser.fz-juelich.de/record/136200},
}