Generic technical position on in situ testing during site characterization for high-level nuclear waste repositories

1990 ◽  
Vol 27 (4) ◽  
pp. 219
Keyword(s):  
Nuclear Waste ◽  
Site Characterization ◽  
In Situ Testing ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Waste Repositories

scholarly journals Towards higher temperatures in nuclear waste repositories

2020 ◽  
Vol 205 ◽  
pp. 01001
Author(s):  
Antonio Gens ◽  
Ramon B. de Vasconcelos ◽  
Sebastià Olivella
Keyword(s):  
Nuclear Waste ◽  
Large Scale ◽  
Maximum Temperature ◽  
Spent Fuel ◽  
Thermally Induced ◽  
Large Scale Field ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Host Rocks ◽  
Waste Repositories

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.

scholarly journals A full-scale in situ heating test for high-level nuclear waste disposal: observations, analysis and interpretation

Géotechnique ◽  
2009 ◽  
Vol 59 (4) ◽  
pp. 377-399 ◽  
Author(s):  
A. Gens ◽  
M. Sánchez ◽  
L. Do N. Guimarães ◽  
E. E. Alonso ◽  
A. Lloret ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Waste Disposal ◽  
Nuclear Waste Disposal ◽  
Full Scale ◽  
High Level Nuclear Waste ◽  
In Situ Heating ◽  
Heating Test ◽  
High Level

scholarly journals UO2 as New Filling Material for Cesium Retention in High-Level Nuclear Waste Repositories

2015 ◽  
Vol 32 (10) ◽  
pp. 854-857
Author(s):  
Albert Martínez-Torrents ◽  
Javier Giménez ◽  
Joan de Pablo ◽  
Ignasi Casas
Keyword(s):  
Nuclear Waste ◽  
Filling Material ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Waste Repositories

In Situ Radiation Damage Studies of Ca3Zr2FeAlSiO12 and Ca3Hf2FeAlSiO12

2008 ◽  
Vol 1124 ◽  
Author(s):  
Karl R Whittle ◽  
Mark Blackford ◽  
Gregory R Lumpkin ◽  
Katherine L Smith ◽  
Nestor J Zaluzec
Keyword(s):  
Nuclear Waste ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Voltage Electron ◽  
Significant Difference ◽  
User Facility ◽  
High Level Nuclear Waste ◽  
Nuclear Waste Immobilization ◽  
High Level

AbstractGarnets, A3B2C3O12, are considered to be potential host phases for the immobilization of high-level nuclear waste as they can accommodate a number of elements of interest, including Zr, Ti and Fe. The naturally occurring garnet, kimzeyite, Ca3(Zr,Ti)2(Si,Al,Fe)3O12, can contain ˜30wt% Zr. An understanding of the radiation tolerance of these materials is crucial to their potential use in nuclear waste immobilization. In this study two synthetic analogues of kimzeyite of composition Ca3Zr2FeAlSiO12 and Ca3Hf2FeAlSiO12 were monitored in situ during irradiation with 1.0 MeV Kr ions using the intermediate voltage electron microscope-Tandem User Facility (IVEM) at Argonne National Laboratory. The structure of these materials was previously determined by neutron diffraction and 57Fe Mössbauer spectroscopy. Ca3Zr2FeAlSiO12 and Ca3Hf2FeAlSiO12 have very similar structural properties with cubic Ia3d symmetry, the only significant difference being the presence of Zr and Hf, respectively, on the 6 coordinated B sites.

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