State Enterprise Radioactive Waste
State Enterprise “Radioactive Waste” Present and Future Challenges Georgi Gyoshev
State Enterprise Radioactive Waste
Fund RAW MEET, MF Expert Working Group
Ministry of EET
BNRA MEW
SE RAW
MH MIE
Executive Director
SD RAWKozloduy
SD Novi Khan Repository
SD Decommissioning Kozloduy
SD NDF
State Enterprise Radioactive Waste Manipulation, pre-treatment, treatment, conditioning, storage and disposal
Transport of RAW State Enterprise Radioactive Waste
• ASUNE Art. 78 • Commerce Act Art. 62 (1)
Construction, operation, rehabilitation, reconstruction of RAW management facilities
• Non-commercial Company Decommissioning of RAW management facilities
Decommissioning of Kozloduy units 1-2
State Enterprise Radioactive Waste
Strategy for management of SF and RAW State Enterprise Radioactive Waste
Organization of Activities
Three-years programs
One-year programs Operational Maintenance Investment
Special
State Enterprise Radioactive Waste
Processing of RAW: Pre-treatment of solid RAW – collection, sorting, decontamination of metal RAW and cutting Treatment of solid RAW – packaging in 200 L drums, precompaction (50 t), super-compaction (910 t) Conditioning of solid RAW in reinforced concrete containers (RCC)
Line “Liquid RAW”
Evaporation of liquid RAW, cementation and packaging in reinforced concrete containers Accumulated RAW for 2009: 463 m3 liquid RAW 1 450 m3 compactable RAW. 84,6 t metal RAW. Decontamination of metallic RAW
State Enterprise Radioactive Waste
Installation for treatment of solid RAW
Sorting
Buffer Storage
Pre-compaction
Super-compaction
Closing
Measurement
Packaging in RCC
State Enterprise Radioactive Waste
RAW storage
• RAW Storage Facility total capacity - 1920 RCC on 31.12.09 - 943 RCC • Lime Plant Site Trench Storage Storage of processed solid waste Site №1 and Site №2 Site for storage of ISO containers
State Enterprise Radioactive Waste
Reinforced concrete container testing
State Enterprise Radioactive Waste
Management of institutional RAW
- Compliance checks - Transportation -Waste acceptance - Treatment - Conditioning - Storage - Radiation monitoring - Dosemetric control
State Enterprise Radioactive Waste
Institutional RAW from: •Industry •Science and research •Agriculture •Medicine
State Enterprise Radioactive Waste Specialized division “Novi Khan Repository”
RAW accepted in 2009: Cs-137 23,475%
4 968 smoke detectors (6 527 sources), 31 GBq 38 spent
241Am
969 spent
239Pu
Pu* 9,391%
sources, 922 GBq
Pu/Be 6,624%
Am/Be 0,388% Cd-109 0,002% H-3 0,102%
94 spent sealed sources
I-129 0,001%
Ra-226 2,197%
sources, 172 GBq 137Cs,
Am-241 54,121%
430 GBq;
Sr-90; Y 0,020%
Други 0,000%
Sr-90;Co-60; Cs-137 0,005%
Tl-204 0,001%
Kr-85 0,204%
82 spent sealed sources
60Со,
24.9 GBq
3 Neutron surces Pu/Be , Am/Be, 129.12 GBq
Ni-63 0,089% Pu-239 0,011% Sr-90 0,108%
ПИЙД 1,691%
Th-232 0,040%
Fe-55 0,046% Eu-152 0,033%
491.1 kg DU shieldings 101 checks for compliance 109 transfers of RAW
C-14 Ba-133 0,061% 0,027%
SKB Meeting 1 July 2010
Co-60 1,360%
H-3 Други Tl-204 I-129 Cd-109 Sr-90;Co-60; Cs-137 Pu-239 Sr-90; Y Ba-133 Eu-152 Th-232 Fe-55 C-14 Ni-63 Sr-90 Kr-85 Am/Be Co-60 ПИЙД Ra-226 Pu/Be Pu* Cs-137 Am-241
State Enterprise Radioactive Waste CHALLENGES – Development of National Disposal Facility for Low- and Intermediate Level Waste
Decision of the Council of Ministers 683/25.06.2005
Development of documents for license application
State Enterprise “Radioactive waste” CHALLENGES – Development of National Disposal Facility Regulatory requirements Modern technologies and good practices
Development of conception and planning Data collection and region analyses Site characterization Confirmation of the selected site Facility design Facility construction Facility commissioning Operation of the disposal facility Closure of the facility Institutional control
The safety of the disposal facility during operational and post-operational phase is assured by engineered and natural barriers and does not depend on any active measures according to the safety criteria
State Enterprise “Radioactive Waste” PROJECT SCHEDULE Strategy on management of spent nuclear fuel and radioactive waste, Council of Ministers, December 2004 Site Selection
1. Development of Concept 2. Data Collection & Analyses of areas 3. Site Characterization 4. Site Confirmation
Civil Construction Works
Design ’06-07
Permit, 05.05.2006
’08 ’08
доклад ’09
’10
’11
’12
’13
’14
Institutional control 300
Operation 2015-2075
Closure
The safety of the disposal facility during operational and post-operational phase is assured by engineered and natural barriers and doesn’t depend on any active measures according to the safety criteria
State Enterprise “Radioactive Waste” Characterization of sites 2008 Marichin Valog, Radiana, Brestova Padina, Varbitza 1.
Complex analysis of regional geophysical fields
2.
Analysis of high accuracy geodesic measurements, geomorphologic and geotectonic surveys
3.
Geological, hydrogeological, engineeredgeological survey of Marichin Valog, Brestova Padina, Varbitza
4.
Characterization of Radiana site
5.
Geophysical survey of Radiana site
6.
Additional study of Radiana site
7.
Migration studies Marichin Valog, Brestova Padina, Varbitza
8.
Migration studies for Radiana site
9.
Summarization of results and selection of preferred site for site confirmation phase
State Enterprise “Radioactive Waste” Comparative assessment of the 4 sites 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. 23.
Location Lithology & Stratigraphy Tectonic & neotectonic settings Geomorphologic settings Geotechnical settings Geochemical characteristics Hydrogeological settings incl. r.n.migration Seismisity Surface dynamic processes (exogenic processes) Flooding Meteorological processes and events Industrial hazard Water and mineral resources Land property and land use RAW transport Demography Flora and fauna National cultural and historical valuable Nuclear experience of the population Infrastructure Possible effect on economic activities Closeness to a state border Public acceptability
1 2
3
4
1 – Radiana – PREFERED SITE 2 – Marichin Valog 3 – Varbitza 4 - Brestova Padina
State Enterprise “Radioactive Waste” Site Confirmation studies of Radiana site, 2009
241Am
is retained within the repository structure
137Cs, 90Sr
и 63Ni move at a distance of 1 m after 360, 260, 1300 years Cmax< 1,0 Bq/m3
94Nb, 239Pu, 129I
94Nb
239Pu
reach the aquifer:
- 86 000 years - 1,78.10-3 Bq/L - 83 000 years - 3,89.10-4
Bq/L
129I
- 4 100 years - 5,59.10-3 Bq/L
State Enterprise “Radioactive Waste” Trench type design
State Enterprise “Radioactive Waste” Design comparison and design selection 1) Proven technology and stakeholders acceptability 2) Safety – conventional and radiological 3) Operation 4) Site criteria 5) Procurement 6) Capital cost 7) Operational and maintenance cost 8) Post-operational cost 9) Schedule 10)Risks
State Enterprise “Radioactive Waste” R-Project 1: Preparation of a detailed geodetic map of Radiana site
State Enterprise “Radioactive Waste”
No
Task
2009 Q4
1
Site characterization stage approval
2
Site confirmation stage approval
3
PSAR approval & Administrative order
4
PrePre-disposal monitoring, design activities
5
PrePre-disposal monitoring implementation
6
Site preparation, design activities
7
Site preparation, implementation
8
Technical design & ISAR development
9
Technical design & ISAR approval and permit for construction
10
Civil Construction works
11
License for operation
2010 Q1
Q2
2011 Q3
Q4
H1
H2
2012 H1
H2
2013 H1
H2
2014 H1
H2
2015
State Enterprise “Radioactive Waste” CHALLENGES – Development of Deep Geological Repository for Spent Fuel and High Level waste
Objectives To select a suitable area/locality for final disposal of HLW and SF: deep geological repository (DGR) Approaches Stepwise assessment of the Bulgaria territory according to established selection scheme Selection scheme is based on: Preferrences Requirements Criteria Usability of similar scheme also for surface repository site selection process
State Enterprise “Radioactive Waste” CHALLENGES – Development of Deep Geological Repository for Spent Fuel and High Level waste Selection scheme principles
Preferrences (recomendations)
-generally accepted principles and conditions of geological settings suitability Requirements
-specified principles and conditions of geological settings suitability, obligation to fulfill Criteria
-qualitative and quantitative defined conditions of assessment criteria, limitations for site selection
State Enterprise “Radioactive Waste” CHALLENGES – Development of Deep Geological Repository for Spent Fuel and High Level waste
Basic principles of selection DGR
geological and geomorphological conditions hydrogeological conditions geochemical conditions engineer-geological and geotechnical conditions and feasibility spontaneous natural changes in the future potential anthropogenic negative influence waste transport environmental protection economical and social aspects
State Enterprise “Radioactive Waste” CHALLENGES – Development of Deep Geological Repository for Spent Fuel and High Level waste
Techno scheme type A 1- RAW Container 2- Protective shield 3Filling 4- Metal support 5-Railway on the main plate and beam 6- Solid support 7-Beam, 8 and 9- Longitudinal and transverse support of the beam, 10-„V”-shape platform for situating the containers 11- Anchors 12- Rock massif from clay marl , 13- Soil cover (of ballast) External diameter of the containers dк = 900 mm The mass of the containers is around 10,5 t. External diameter (in black) of the gallery Dч = 4,00 m b1=700 mm, b2=1800 mm, b3=500 mm, h1=350 mm, h2=650 mm
State Enterprise “Radioactive Waste” CHALLENGES – Development of Deep Geological Repository for Spent Fuel and High Level waste Container for disposal of SF and HL RAW
State Enterprise “Radioactive Waste”
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