Published October 1989 | Version v1
Miscellaneous Metadata-only

Combined concept system analysis. Thermal and thermomechanical analysis of the immediate vicinity of the ultimate repository and required area for the repository itself. Final report. Technical annex 5

Creators

  • 1. Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.). Inst. fuer Nukleare Entsorgungstechnik
  • 2. Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.). Projektgruppe Andere Entsorgungstechniken (PAE)

Description

The report contains four papers with the following subjects: 1) Thermal design calculations on various combined concepts for nuclear waste disposal (borehole, tunnel and mixed repositories) of LWR and HTR spent fuel elements and intermediate radioactive wastes; 2) Calculation of required area for the repository; 3) Thermomechanical calculations adjacent to highly active waste and spent fuel element storage sites; 4) Thermomechanical studies on tunnel convergence and stability of fuel element repository tunnels before disposal. (HP)

Availability note (English)

Available from Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.).

Abstract (German)

Der Bericht enthaelt vier Arbeiten mit den Themen: 1) Thermische Auslegungsrechnungen zu verschiedenen gemischten Endlagerkonzepten (Bohrlochlagerung, Streckenlagerung und gemischte Lagerung) fuer LWR-BE, HTR-BE und MAW; 2) Ermittlung des Flaechenbedarfs des Endlagers; 3) Thermomechanische Rechnungen neben HAW und BE-Einlagerungsfeldern; 4) Thermomechanische Untersuchungen zur Streckenkonvergenz und Standsicherheit von BE-Lagerstrecken vor ihrer Befuellung. (HP)

Additional details

Additional titles

Original title (German)
Systemanalyse Mischkonzept. Thermische und thermomechanische Analysen des Endlager-Nahbereichs und Ermittlung des Flaechenbedarfs des Endlagers. Abschlussbericht. Technischer Anhang 5

Publishing Information

Imprint Pagination
141 p.

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
22019752
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COATED FUEL PARTICLES; DISTANCE; GORLEBEN SALT DOME; HIGH-LEVEL RADIOACTIVE WASTES; INTERMEDIATE-LEVEL RADIOACTIVE; MULTI-PARAMETER ANALYSIS; RADIOACTIVE WASTE DISPOSAL; SALT CAVERNS; SPENT FUEL ELEMENTS; THERMODYNAMICS; UNDERGROUND DISPOSAL
Descriptors DEC
CAVITIES; FUEL ELEMENTS; FUEL PARTICLES; MANAGEMENT; MATERIALS; NUCLEAR FACILITIES; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTES; REACTOR COMPONENTS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES

Optional Information

Contract/Grant/Project number
Contract BMFT KWA 2190 A1