Disused Sealed Radioactive Sources (DSRS)

Transcription

1 French Experience of DSRS Management (Session 6) International Conference on the Safety and Security of Radioactive Sources: Maintaining continuous global control of sources throughout their life cycle Abu Dhabi, UAE, October 2013 (IAEA-CN-204) Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / b/ Session 6 Disused Sealed Radioactive Sources (DSRS) When a radioactive source becomes disused: The risk of future loss of control is increased The source may remain dangerous for many years Safety, security and radiological protection are at stake My presentation will focus on the management of DSRS in France and propose conclusions that should fit to any country Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 2 1

2 Management of DSRS as RS or radioactive material According to French regulation ( Public Health Code ): RS become DSRS: if they are no more used or after 10 years (can be extended to 15 or 20 years with authorization) DSRS shall not remain on the site where they were used DSRS shall be collected by the supplier and then can be : Sent back to the supplier or to the country of origin Sent to a producer for recycling Stored before decision or before a planned solution is available Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 3 Management of DSRS as radioactive waste Management of DSRS as radioactive waste needs to enter into the regulation of the environment code. The law, revised in 2006, introduces a national roadmap for the management of radioactive waste (PNGMDR) with the following objectives: Establish a definition of radioactive waste categories Seek long-term management solutions for every category of radioactive waste Take due account of public concerns All existing or planned final disposal facilities in France are or will be operated by ANDRA (National Agency) Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 4 2

3 Existing or planned ANDRA final disposal facilities, and general criteria for radioactive waste half-life Waste Activity Short half-life ( Cs 137) Long half-life (> Cs 137) Very Low Level (VLL) Surface disposal (CSTFA) Low Level (LL) Intermediate Level (IL) High Level (HL) Surface disposal (CSFMA) except some tritiated waste and some sealed sources Dedicated sub-surface Facility under study (FAVL) Ongoing studies, including disposal in deap geological Repository (MAVL-HAVL) Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 5 Additional Criteria for acceptance of DSRS in final disposal (1) The general criteria above are completed for each category of waste and for each disposal by detailed criteria. Criteria concerning DSRS take into account the specific features of sources: Radioactivity is concentrated in a (very) small volume Shielding of DSRS (or batch of DSRS) is often needed Radioactive inventory is (in most cases) very well known DSRS may remain attractive after a long time in disposal, whenever an intrusion in disposal would occur Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 6 3

4 Additional criteria for acceptance of DSRS in final disposal (2) ANDRA Disposal Sites DSRS Criteria Half life VLL CSTFA Morvilliers No activity (1 Bq) after 30 years < 1year LL CSFMA Soulaines * Low activity after 300 years (Detailed criteria are available ) IL Subsurface FAVL Low activity after 500 years < 31 years ** All*** HL Geological Bure MAVL / HAVL All other DSRS All * Tritium DSRS will need a long interim storage due to very low acceptance criteria in CSFMA ** LAS (activity limit per source) for all half-lives above 10 years *** LAS (activity limit per source) not yet available Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 7 and GIP sources HA strategy (1) During many years, and CISBIO were the principal producers and suppliers of SRS in France, and have the responsibility for collection and management of these DSRS Since 2009, and CISBIO cooperate on this task through a public interest group, the GIP Sources HA. Due to limited storage capacities, and to security and safety concerns, indefinite interim storage of collected DSRS is not a solution: each DSRS must be eliminated. DSRS management strategy requires a transport strategy in support. Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 8 4

5 & GIP strategy (2) Major pathways for the management of DSRS as radioactive material (potentially reusable) Collectingsites CIS BIO Management priorto decisionto dispose of as waste Return to supplier or country of origin Recycling by a manufacturer Marcoule Storage awaiting decision or availability of a specific pathway Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 9 & GIP strategy (3) Major pathways for DSRS after decision to handle them as waste Collecting sites Processing Interim Storage CIS BIO Marcoule CIS BIO Cadarache Marcoule Cadarache Marcoule ANDRA Final Diposal CSTFA Morvilliers CSFMA Soulaines MAVL Bure HAVL Bure 12 facilities will be used in 6 locations Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session

6 Disposal Sources to be managed Number Activity (TBq) CSTFA Surface disposal CSFMA MAVL HAVL Surface disposal < 120 watts / package Geological disposal < 10 watts / package & GIP strategy (4) * Geological disposal < 200 watts / package * Americium-241 smoke detector DSRS Waste Package 1 m 3 Metallic basket 5 m 3 Cement package 1 m 3 Cement package 0,2 m 3 Metallic drum Total Volume (m 3 ) 4 m m m 3 1 m 3 Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 11 DSRS Working Group in PNGMDR A specific working group is now in place in the framework of PNGMDR and will propose a national strategy for the management of all DSRS in France by the end of 2014 This group will take due account of the work and developments already made or planned by, GIP and ANDRA and check that each type of DSRS will finally find a possible way to an existing or planned disposal through an existing or planned waste management process Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session

7 Proposed general recommendations derived from French experience A/ Safe and secure storage is a necessary first step (DSRS should not remain in the place where they were used) At least one national interim storage is needed B/ Inventory of the national storage should be minimised and secured by the following actions: Return to the supplier (replacement contracts should be encouraged) Return to the country of origin Export to a producer for recycling Condition DSRS in long term storage packages, adequate for future disposal Maintain packages, devices and storage in good / safe / secure conditions Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session 6 13 Proposed general recommendations derived from French experience C/ Manage as radioactive waste A national strategy for the management of radioactive wastes is necessary This strategy should include DSRS, with due consideration of the specificities transport solutions are needed for A + B + C More services from the Industry should be developed, with contributions of Sources and Transport operators Harmonization of international requirements and best practices for DSRS transports / import / export would help to improve efficiency Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session

8 French Experience of DSRS Management Thank you for your attention and your questions Abu Dhabi (IAEA-CN-204) French Experience of DSRS Management, Bernard Sevestre / / Session