Coupled THM Analysis of a Full-Scale Test for High-Level Nuclear Waste and Spent Fuel Disposal Under Actual Repository Conditions During 18 Years of Operation

Géotechnique ◽  
2021 ◽  
pp. 1-43
Author(s):  
Marcelo Sánchez ◽  
Beatrice Pomaro ◽  
Antonio Gens
2020 ◽  
Vol 205 ◽  
pp. 01001
Author(s):  
Antonio Gens ◽  
Ramon B. de Vasconcelos ◽  
Sebastià Olivella

Recently, there is a tendency to explore the possibility of increasing the maximum design temperature in deep geological repositories for high-level nuclear waste and spent fuel. In the paper, a number of issues related to the use of higher temperatures are reviewed. Both bentonite barriers and argillaceous host rocks are addressed. An application involving the modelling of a large-scale field test conducted at a maximum temperature of 140ºC is presented. It is shown that currently available theoretical formulations and computer codes are capable to deal with temperatures above 100ºC and to reproduce satisfactorily the thermally-induced overpressures in the rock.


Géotechnique ◽  
2009 ◽  
Vol 59 (4) ◽  
pp. 377-399 ◽  
Author(s):  
A. Gens ◽  
M. Sánchez ◽  
L. Do N. Guimarães ◽  
E. E. Alonso ◽  
A. Lloret ◽  
...  

Author(s):  
Reinhold Graf ◽  
Wolfgang Filbert ◽  
Klaus-Ju¨rgen Brammer ◽  
Wilhelm Bollingerfehr

The “direct disposal of spent fuel” as a part of the current German reference concept was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this part of the reference concept, the so called POLLUX® concept, i.e. interim storage buildings for casks containing spent fuel, a pilot conditioning facility, and a special cask “POLLUX” for final disposal have been built. With view to a geological salt formation all handling procedures for the direct disposal of spent fuel were tested aboveground in full-scale test facilities. To optimise the reference concept, all operational steps have been reviewed for possible improvements. The two additional concepts for the direct disposal of SF are the BSK 3 concept and the DIREGT concept. Both concepts rely on borehole emplacement technology, vertical boreholes for the BSK 3 concept und horizontal boreholes for the DIREGT concept. Supported by the EU and the German Federal Ministry of Economics and Technology (BMWi), DBE TECHNOLOGY built an aboveground full-scale test facility to simulate all relevant handling procedures for the BSK 3 disposal concept. GNS (Company for Nuclear Service), representing the German utilities, provided the main components and its know-how concerning cask design and manufacturing. The test program was concluded recently after more than 1.000 emplacement operations had been performed successfully. The BSK 3 emplacement system in total comprises an emplacement device, a borehole lock, a transport cart, a transfer cask which will shuttle between the aboveground conditioning facility and the underground repository, and the BSK 3 canister itself, designed to contain the fuel rods of three PWR-fuel assemblies with a total of about 1.6 tHM. The BSK 3 concept simplifies the operation of the repository because the handling procedures and techniques can also be applied for the disposal of reprocessing residues. In addition to this, the feasibility of the direct disposal of transport and storage casks, the so-called “DIREGT concept”, is being investigated. The implementation of this concept would avoid the necessity to separate fuel rods from structural parts and to procure custom-made final disposal casks. All investigations and studies performed so far support the feasibility of direct disposal of spent fuel in multipurpose casks as today used for transport and storage. Both additional concepts, BSK 3 and DIREGT, are expected to simplify disposal processes and to reduce operational risk without any compromise in long-term radiological safety aspects.


1996 ◽  
Vol 465 ◽  
Author(s):  
Patrik Sellin ◽  
Jordi Bruno ◽  
Ester Cera

ABSTRACTIn a safety analysis of a repository for high level nuclear waste, it is of primary importance to identify and document all processes that are acting on the repository system. An interaction matrix methodology have been applied to the spent fuel subsystem. The purpose of this application is to identify, structure and rank the Process System and to discuss how the identified processes can be treated.


1994 ◽  
Vol 1 (1) ◽  
pp. 77-83
Author(s):  
Yoshiji Moro ◽  
Tomoo Fujita ◽  
Takeshi Kanno ◽  
Akira Kobayashi

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