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    • CFM - Colloid Formation & MigrationCFM - Colloid Formation & Migration
    • C-FRS - CRIEPI’s Fractured Rock StudiesC-FRS - CRIEPI’s Fractured Rock Studies
    • CIM - Carbon-14 and Iodine-129 Migration in CementCIM - Carbon-14 and Iodine-129 Migration in Cement
    • ESDRED / TEM -Test and Evaluation of Monitoring SystemsESDRED / TEM -Test and Evaluation of Monitoring Systems
    • FEBEXe - Full-scale Engineered Barriers ExperimentFEBEXe - Full-scale Engineered Barriers Experiment
    • FEBEX-DP - Febex Dismantling ProjectFEBEX-DP - Febex Dismantling Project
    • FORGE - Laboratory Column ExperimentsFORGE - Laboratory Column Experiments
    • GAST - Gas-Permeable Seal TestGAST - Gas-Permeable Seal Test
    • HotBENT - High Temperature Effects on Bentonite BuffersHotBENT - High Temperature Effects on Bentonite Buffers
    • ISC - In-situ Stimulation & Circulation ExperimentISC - In-situ Stimulation & Circulation Experiment
    • LASMO - Large Scale MonitoringLASMO - Large Scale Monitoring
    • LCS - Long-Term Cement StudiesLCS - Long-Term Cement Studies
    • LTD - Long Term DiffusionLTD - Long Term Diffusion
    • MaCoTe The Material Corrosion TestMaCoTe The Material Corrosion Test
    • NF PRO - Near Field ProcessesNF PRO - Near Field Processes
    • PSG - Pore Space GeometryPSG - Pore Space Geometry
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Disposal of Radioactive Waste

Grimsel's Role in Research

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By Administrator
Administrator
Parent Category: GTS Background Information
Category: Disposal of Radioactive Waste
22 April 2009
22 April 2009
Last Updated: 22 June 2021

Its all very well to design a waste disposal system - but how do you know that it will work ?

This is where the Grimsel Test Site (GTS) comes in - with experiments to test the long term behaviour of the engineered barriers, to develop and test tools to confirm the suitability of potential geological host rocks and to test the models used to predict its performance as a long-term barrier to radionuclide release.

Many countries have plans for repositories but in order to ensure that their designs will work, they need somewhere to test out their concepts for safe waste disposal.

These tests should be carried out in similar conditions to a repository. The GTS is a research facility several hundred metres underground which provides a relevant environment for equipment, methodology and model tests.

The GTS is a scientific test site and not a potential repository site; although investigations may utilise a wide range of radioactive tracers, no radioactive waste will be disposed of at the GTS.

All experiments utilising a radioactive tracer are supervised by a Radiation Protection Expert (RPE) and follow very strict regulations which were set by HSK (Hauptabteilung für die Sicherheit der Kernanlagen / Swiss Federal Nuclear Safety Inspectorate - now ENSI ) and continues with BAG (Bundesamt für Gesundheit / Swiss Federal Office of Public Health).

Click here for details on radiation protection at the GTS.

reference disposal 2021Nagra's high level waste (HLW) disposal concept - cutaway. View The Engineered Barrier System section

Safety Barriers

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By Administrator
Administrator
Parent Category: GTS Background Information
Category: Disposal of Radioactive Waste
18 February 2009
18 February 2009
Last Updated: 30 July 2014

A multi-barrier approach ensures the long-term isolation of radioactive waste and is the adopted solution of preference for radioactive waste management. The Engineered Barrier System (EBS) is one part of this passive multi-barrier system approach and it refers to all barriers introduced through technological (engineered) activities. It is complemented by the natural barrier, also referred to as the geological barrier or geosphere.
 

 Components of the EBS for High Level Waste (HLW) and Spent Fuel (SF)

In a deep geological repository, safe long-term containment of the waste is provided by a system consisting of three engineered barriers and one geological barrier.

In the case of spent fuel, the cladding containing the uranium pellets represents the first engineered barrier. Packaged in thick-walled metal containers (second engineered barrier), the fuel elements are placed on a bentonite plinth in the disposal tunnel and the entire tunnel is backfilled with bentonite granulate (third engineered barrier). Together with the overlying formations, the host rock forms the geological barrier.

High-level fission product solutions from reprocessing are immobilised in a glass matrix that corrodes extremely slowly. The metal containers and the bentonite backfill again represent the other two engineered barriers

The Grimsel Full-scale Engineered Barriers Experiment (FEBEX) project has been examining the emplacement of a steel canister within a bentonite backfilled tunnel. A more detailed overview from the Swiss approach is shown below:

{flv width="550" height="340" usefullscreen="true" img="videos/HLW_emplacement_thumb.jpg" captions="/images/stories/videos/emplacement_st.xml"}Emplacement{/flv} 

 Components of the EBS for Low/Intermediate Level Waste (L/ILW)

The repository for low- and intermediate-level waste has four different safety barriers - three engineered and one geological.

The waste is solidified in a matrix and enclosed in drums (first engineered barrier).

Several of these drums are placed in a concrete container which is filled with cement (second engineered barrier).

The concrete containers are stacked on top of and adjacent to one another in large caverns and the spaces between the containers are backfilled with a special mortar (third engineered barrier).

Together with the overlying formations, the host rock forms the geological barrier.

As the EBS for L/ILW waste is constructed mostly from concrete, the effect of such a large cementitous mass on the rock and water systems is being investigated directly by in situ Grimsel projects such as Gas Migration in EBS and Geosphere (GMT), Hyperalkaline Plume in Fractured Rock (HPF) and Long-Term Cement Studies (LCS).

{flv width="550" height="340" usefullscreen="true" img="videos/LLW_emplacement_thumb.jpg" captions="/images/stories/videos/llw_st.xml"}LLW_emplacement{/flv}

Deep geological disposal - Far field

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By Administrator
Administrator
Parent Category: GTS Background Information
Category: Disposal of Radioactive Waste
16 February 2009
16 February 2009
Last Updated: 30 July 2014

A series of emplacement tunnels will be constructed deep underground to house the HLW and SF canisters. An example layout for a SF/HLW repository and an operational study (surface facilities, emplacement tunnels, pilot tunnels, rock laboratory, access ramp, ventilation tower, etc.) has been developed by Nagra.

{flv width="550" height="340" usefullscreen="true" img="videos/HLW_overview_thumb.jpg"}Overview{/flv}

Video overview of a possible tunnel layout for a SF/HLW repository, designed for a sedimentary formation

The images below are stills taken from the Nagra Die LÖSUNG DVD which outlines the procedures and methods for the remote emplacement of a HLW / spent fuel canister.  Please see the Media & Downloads section for additional videos on geological emplacement.

A picture
Overview of Deep Geolgical Disposal - click for larger image

A picture
Emplacement tunnels - click for larger image

A picture
Pilot tunnels - click for larger image

A picture
Underground rock laboratory area - click for larger image

A picture
Access ramp - click for larger image

A picture
Repository situated at a depth ~600m - click for larger image

 

Types of Radioactive Waste

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By Administrator
Administrator
Parent Category: GTS Background Information
Category: Disposal of Radioactive Waste
11 February 2009
11 February 2009
Last Updated: 30 July 2014

Waste generation in Switzerland
Different types of radioactive waste and their sources in Switzerland

The Nuclear Energy Ordinance in Switzerland distinguishes the following categories of waste.

Art. 51 Categories of radioactive waste
For the purpose of disposal, radioactive waste is divided into the following categories:
 

  • high-level waste (HLW):
    • spent fuel (SF) not destined for reprocessing;
    • vitrified fission product solutions from reprocessing of spent fuel;
  • alpha-toxic waste (ATW): waste with a content of alpha-emitters exceeding a value of 20,000 Becquerels per gram of conditioned waste;
  • low- and intemediate-level waste (L/ILW): all other radioactive waste.

For disposal, Nagra allocates the waste to different repository types:







Deep geological repository for HLW/SF for spent fuel and vitrified fission product solutions from reprocessing.

Deep geological repository for low- and intermediate-level waste (L/ILW). 

 

 

 

Spent Fuel (SF) rods canister design
HLW vitrified waste canister design
L/ILW low/intermediate level disposal drum

Overview of Radioactive Waste Disposal

Details
By Administrator
Administrator
Parent Category: GTS Background Information
Category: Disposal of Radioactive Waste
10 February 2009
10 February 2009
Last Updated: 28 June 2021


Radioactive waste materials are generated from medicine, industry, research and power generation.

We consume raw materials and energy on a daily basis. This produces gaseous, liquid and solid wastes. Some of this waste can be recycled and the remainder has to be disposed of safely. Respect for the environment, mankind and biota demands that we find and implement waste management solutions. Radioactive wastes have to be isolated from the human environment for the duration of their toxicity and managed safely. Carefully implemented procedures and proper practices can ensure that no adverse effects will result.

Waste generation in SwitzerlandDifferent types of radioactive waste and their sources in Switzerland

Based on current understanding, many countries, including Switzerland, have concluded that deep geological disposal is the only method for managing radioactive waste that meets the strict requirements relating to long-term safety. Concepts in which safety relies on continuous monitoring by human institutions are not capable of fulfilling these requirements, for long times.

Underground laboratories (URLs), such as Grimsel,  serve an important role in the overall investigation into the long-term disposal of radioactive waste. Together with site-specific tests, laboratory studies and studies of natural analogues, they can assist in developing rigorous databases for the assessment of long-term safety and engineering feasibility of proposed disposal concepts.

The Swiss Federal Council and Parliament have decided that all waste arising in Switzerland will undergo deep geological disposal.

The Grimsel Test Site (GTS) is a scientific test site and not a potential repository site; although investigations may utilise a wide range of radioactive tracers, no radioactive waste will be disposed of at the GTS.

GTS Partners Information

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  • The Geology of the GTS
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The GTS Experiments

Grimsel experiments which are relevant to the high level waste (HLW) concept are :

  • CFM - Colloid Formation and Migration experiment
  • C-FRS - CRIEPI's Fractured Rock Studies
  • ESDRED / TEM - Test and Evaluation of Monitoring Systems
  • FEBEX - Full-scale Engineered Barriers Experiment
  • FEBEXe - Full-scale Engineered Barriers Experiment extended
  • FEBEX-DP - FEBEX Dismantling Project
  • LCS - Long Term Cement studies
  • LTD - Long Term Diffusion experiment

Grimsel experiments which are relevant to the low level waste (LLW) concept are :

  • CFM - Colloid Formation and Migration experiment
  • C-FRS - CRIEPI's Fractured Rock Studies
  • FORGE - Laboratory Column Experiments 
  • GAST - Gas-Permeable Seal Test
  • LCS - Long Term Cement studies
  • LTD - Long Term Diffusion experiment
  • PSG - Pore Space Geometry eexperiment

Non specific experiments :

  • HotBENT - High Temperature Effects on Bentonite Buffers

The background on the different methods used for HLW and LLW emplacement can be found here :

  • Disposal : The Engineered Barrier System
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