Can the Kristallin-I near-field model be considered robust?

Conference · Thu Dec 31 00:00:00 EST 1992

OSTI ID:103038

McKinley, I G ^[1]; Smith, P A; Curti, E ^[2]

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1. Nagra, Wettingen (Switzerland)
2. Paul Scherrer Institut, Villigen (Switzerland)

Kristallin-I is an integrated analysis of the disposal of HLW in the crystalline basement of Northern Switzerland which incorporates the findings of the Phase I (regional) geological investigations of this host rock. The disposal concept and the performance assessment methodology are effectively the same as those in the earlier Project Gewaehr study, although individual models and databases have developed somewhat in the last 6 years. In particular, more credit is now taken for the engineered barriers in the near-field. The emphasis on a more realistic treatment of the engineered barriers is important as the HLW programme moves away from feasibility studies towards host rock/site selection. Nevertheless, in performance assessment it is essential that the models used are demonstrably conservative in view of all uncertainties involved - i.e. are robust (this terminology is discussed by McCombie). This paper reviews the base-case model for radionuclide release from the near field and compares this with best estimates of the expected behaviour in order to evaluate, as quantitatively as possible, some of the uncertainties associated with model simplifications. This comparison forms the basis to answer the question posed in the title of this paper.

• OSTI ID: 103038
• Report Number(s): CONF-920430-Vol.2; TRN: 95:019844
• Resource Relation: Conference: 3. international high level radioactive waste management (IHLRWM) conference, Las Vegas, NV (United States), 12-16 Apr 1992; Other Information: PBD: 1992; Related Information: Is Part Of High level radioactive waste management: Proceedings. Volume 2; PB: 1238 p.
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
SWITZERLAND
RADIOACTIVE WASTE FACILITIES
HIGH-LEVEL RADIOACTIVE WASTES
UNDERGROUND DISPOSAL
PERFORMANCE
CONTAINMENT SYSTEMS
SITE SELECTION
TIME DEPENDENCE
FISSION PRODUCT RELEASE
CONTAINERS
FAILURES
MATHEMATICAL MODELS
BENTONITE