France
Waste Classification and Policy
The French classification of waste is defined by a ministerial decree related to the National
management plan of radioactive materials and waste updated every three years. In continuity
with past practices, the Decree No. 2013-1304 of 27 December 2013 provides a classification
based on two parameters: the level of radioactivity and the half-life of the radionuclides present
in the waste. As a function of the level of radioactivity, waste are split into very low level
(generally less than one hundred Becquerel per gram), low level (between a few tens and a few
hundred thousand Becquerel per gram), intermediate level (of the order of 1 million to 1 billion
Becquerel per gram), high level (of the order of several billion Becquerel per gram). On the basis
of the half-life can be distinguished so called very short-lived waste (half-life less than
100 days), short-lived waste, whose radioactivity is mainly due to radionuclides that have a
period not exceeding 31 years, long-lived waste, which contain a significant amount of
radionuclides whose half-life is greater than 31 years.
The long term management of each type of waste requires the implementation or development of
specific facilities, appropriate to the danger it presents and its evolution over time. To define
long term management solutions, six waste categories can be distinguished: high level waste
(HA) and intermediate level long-lived waste (MAVL) are planned to be disposed of in a deep
geological repository subject to authorization (Cigéo Project); low level long-lived waste (FAVL)
are also the subject of studies and research to develop disposal solutions, mainly based on so
called low depth or shallow repository; low and intermediate short-lived waste (FMA-VC) are
being currently disposed of in surface repository under operation (Centre de stockage de l’Aube);
very low level waste are currently disposed of in a dedicated near-surface facility also under
operation; the very short-lived waste (VTC) are managed locally by radioactive decay and then
disposed of in ordinary waste facilities.
Views of Centre de stockage de l’Aube: disposal of low and intermediate level short-lived waste
The responsibilities of radioactive waste management actors are defined by law. Within this
framework, Andra (national radioactive waste management agency) is the public body in charge
of siting, designing, construction and operation of disposal facilities; the waste producers are
responsible for their waste which includes the funding of their long term management; the
independent regulator ASN (Autorité de sûreté nucléaire) defines safety rules and examines
applications (with the technical support of IRSN - Institut de radioprotection et de sûreté
nucléaire); a committee of independent experts assesses the progress of studies and research for
the French government and parliament (Commission nationale d’évaluation); other stakeholders
are involved at local and national levels.
As operational application of the waste law of 28 June 2006, the National management plan of
radioactive materials and waste (PNGMDR) provides for the various tasks to be implemented to
develop new waste management solutions and optimize existing ones. It is drawn up by a
working group consisting of waste management actors and representatives of environmental and
societal organizations.
Low and intermediate level long-lived waste volumes
A national waste inventory is published by Andra every three years; it is used as reference data
for the PNGMDR.
Low level long-lived waste include graphite waste, waste containing radium and some other
waste such as bituminized sludge from the treatment of effluents in nuclear facilities. Most
graphite waste comes from the dismantling of former natural uranium gas-cooled reactors.
Radium-bearing waste is mostly produced by non-nuclear industrial activities (TE-NORM
waste). The volume of existing waste was 87,000m3 at the end of 2010. The total prospective
volume is estimated at 89,000m3 in 2020 and 133,000m3 in 2030.
Intermediate level long-lived waste arises mainly from spent fuel reprocessing and from the
maintenance and operation of reprocessing plants. These include clads and hulls, as well as
maintenance waste (used tools, equipment ...) and process waste, as some sludge. The volume of
existing waste was 40,000m3 at the end of 2010. The total prospective volume is estimated at
45,000m3 in 2020 and 49,000m3 in 2030.
Planned/ Proposed Disposal Facilities
Long term management of low level long-lived waste
Consistently with the 2006 waste law, a siting process for a “low depth” repository was launched
in 2007 on a volunteering basis. Two volunteer sites were selected but finally withdrew their
candidature. Within the framework of the PNGMDR for the 2010-2012 time-frame, the French
Government charged Andra to re-examine different options for managing graphite and radium
bearing waste and to continue dialogue in view of siting. These options include potential sorting
and/or treatment of the waste and their disposal. Andra provided the Government by the end of
2012 with a report outlining different possible management scenarios and a new approach for
siting continuation. Therefore a field geological survey was launched in 2013 for the
implementation of a shallow repository. On the basis of geological investigations that may be
carried over the period 2013-2015, continued characterization of waste, specific research on the
treatment of waste and safety analysis, Andra is in charge to issue a new report in 2015
containing: (i) the feasibility analysis of considered management scenarios for graphite and other
waste; (ii) a feasibility study of a shallow repository including the scope of waste that might be
accommodated and a timetable for its implementation.
The shallow disposal concept consists of a repository implementation within a low permeability
clay layer at a depth of about 15 meters provided the host formation is outcropping (see figure
below). Once completed, the pits are covered with a layer of compacted clay excavated from the
site and stored prior to its reuse. The waste isolation and containment capability is available as
long as the geodynamic site evolution does not significantly modify the repository configuration
(i.e. via erosion). With regard to its depth and the expected geodynamic conditions, the stability
of the repository is estimated to be about 50,000 to 100,000 years.
The shallow disposal concept is considered potentially for long-lived waste containing:
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Radionuclides with a low mobility and a half-life such that sufficiently low activities
have been reached by decay in less than 50,000 years. The preservation of physical,
chemical and hydraulic conditions limiting radionuclide mobility should be insured.
Considered radionuclides have a half-life lower or equal to that of Carbon-14
(5,700 years). It covers in particular Radium-226 (1,600 years);
Restricted activity of Plutonium and Americium;
Restricted activity of radionuclides that do not decay sufficiently within 50,000 to
100,000 years such as Thorium-232 and Uranium-238 and Uranium-235;
Restricted activity of long-lived, potentially highly mobile radionuclides.
Waste acceptance criteria will be adapted to site performance as assessed from the results of
geological survey. Design of disposal pits will be adapted to waste characteristics. Waste
packaging will be defined in relation with repository design.
Shallow Disposal Concept
Cigéo deep geological disposal project
The 2006 waste law provides for the operation of a deep geological disposal facility from 2025
for both high level and intermediate level long-live waste, provided licensing. By law deep
geological disposal is dedicated to waste that cannot be disposed of at the surface or at low depth
with regard to safety. The application is currently planned from 2015. In 2011, the results of
20 years of R&D made it possible to issue detailed project technical requirements. On this basis
Andra launched the industrial design of the future facilities of Cigéo Project. A public debate
was held on the project during the year 2013. Recommendations from this debate will be
considered in the next design phases as well as in the preparation of the application.
If licensed the disposal facility will be implemented at a depth of 500m, in the CallovoOxfordian clay layer (argillites) which has been investigated in the Meuse/Haute Marne
Underground research laboratory (URL). The underground facility will be located in a 30km2
defined area close to the URL. This facility is planned to be constructed progressively along with
waste delivery, over a period of about one century. It will include dedicated disposal zones for
intermediate level long-lived waste and high level waste. Access to the underground facility will
be provided by vertical shafts (ventilation, mucking…) and an incline ramp for waste transfer.
Two service areas are planned on the surface: one of them located at the entrance of the ramp
will be dedicated to receiving, control and preparation of waste packages; the other, located
vertically above the underground facility, will support construction.
Disposal cells for intermediate level long-lived waste consist of horizontal tunnels with a 500m
length. The cross section of the disposal tunnels makes it possible to stack waste disposal
packages. Waste handling will be carried out remotely because of the dose rate within the
disposal tunnels.
The Meuse/Haute-Marne Underground research laboratory
Cigéo project
(on the left: disposal cells for intermediate level long-lived waste during operation and after
closure)
The depth of the disposal facility, the absence of exceptional natural resources and the
favourable geodynamic context provide for the isolation of waste during very long periods of
time.
The long-term containment is essentially based on the favourable properties of the host clay
layer. It has been studied at the scale of a million years. Post closure safety functions are:
(i) oppose groundwater flow; (ii) limit the release of radionuclides and immobilize them within
repository; (iii) delay and mitigate the migration of radionuclides. The main geological
properties governing these safety functions are: geodynamic stability, geological continuity and
thickness of the clay layer; low permeability and retardation capability of the argillite; low
hydraulic gradients in the considered area; etc. A number of experiments were carried out in the
URL to assess these properties at pertinent scales. The design of the underground facility aims at
the preservation of these favourable properties in particular with regard to mechanical and
chemical impacts. Underground experiments have being carried out specifically to investigate
the potential interactions between repository and host rock.
The underground architecture of the repository contributes to its long term performance and
robustness (implementation of disposal drifts in the middle part of the clay layer, location of
access shafts and ramps, configuration of disposal zones, etc.).
After operation, disposal cells, access drifts and shafts will be sealed and backfilled to fulfil post
closure safety functions. Significant work has been done to develop and demonstrate the
capability to seal the repository.
Safety studies have included a number of iterations since the first French waste law in 1991 to
progressively optimize the conceptual design with regard to safety. The safety case provided by
Andra in 2005 showed the scientific feasibility and the long term safety of a deep disposal
facility in the clay layer investigated in the URL.
Along with safety, reversibility of deep geological disposal is a requirement of the 2006 waste
law. Provisions are included in the design to enhance the retrievability of disposed waste
packages. The implementation, the operation and the closure of the disposal facility are
conceived as a stepwise and progressive process. Intermediate milestones will be identified until
final closure to adapt as necessary the conduct of operation and closure.
References
Inventaire national des matières et déchets radioactifs 2012 : Rapport de synthèse - www.andra.fr
Plan national de gestion des matières et des déchets radioactifs - http://www.developpementdurable.gouv.fr
Projet Cigéo : Centre industriel de stockage réversible profond de déchets radioactifs en
meuse/haute-marne - Dossier du maître d’ouvrage 2013 - www.andra.fr
Propositions de l'Andra relatives à la réversibilité du projet Cigéo 2013 - www.andra.fr