Details zur Publikation

Kategorie Textpublikation
Referenztyp Zeitschriften
DOI 10.13182/NT08-A3974
Titel (primär) Results from an international simulation study on coupled thermal, hydrological, and mechanical processes near geological nuclear waste repositories
Autor Rutqvist, J.; Barr, D.; Birkholzer, J.T.; Chijimatsu, M.; Kolditz, O. ORCID logo ; Liu, Q.; Oda, Y.; Wang, W. ORCID logo ; Zhang, C.
Quelle Nuclear Technology
Erscheinungsjahr 2008
Department ENVINF
Band/Volume 163
Heft 1
Seite von 101
Seite bis 109
Sprache englisch
Abstract As part of the ongoing international DECOVALEX project, four research teams used five different models to simulate coupled thermal, hydrological, and mechanical (THM) processes near waste emplacement drifts of geological nuclear waste repositories. The simulations were conducted for two generic repository types, one with open and the other with back-filled repository drifts, under higher and lower postclosure temperatures, respectively. In the completed first model inception phase of the project, a good agreement was achieved between the research teams in calculating THM responses for both repository types, although some disagreement in hydrological responses is currently being resolved. In particular, good agreement in the basic thermal-mechanical responses was achieved for both repository types, even though some teams used relatively simplified thermal-elastic heat-conduction models that neglected complex near-field thermal-hydrological processes. The good agreement between the complex and simplified process models indicates that the basic thermal-mechanical responses can be predicted with a relatively high confidence level.
dauerhafte UFZ-Verlinkung https://www.ufz.de/index.php?en=20939&ufzPublicationIdentifier=1385
Rutqvist, J., Barr, D., Birkholzer, J.T., Chijimatsu, M., Kolditz, O., Liu, Q., Oda, Y., Wang, W., Zhang, C. (2008):
Results from an international simulation study on coupled thermal, hydrological, and mechanical processes near geological nuclear waste repositories
Nucl. Technol. 163 (1), 101 - 109 10.13182/NT08-A3974