1. Department for low and intermediate level waste Börje Torstenfelt
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2. This gives an overall picture of the principles for handling and storage of operational and decommissioning waste. We have the operational waste from the power plants, with short-lived going to SFR, long-lived goes to Clab or a special interim storage until the final repository for long-lived waste, the SFL-repository is in operation. The present plan is that it should be in regular operation at Very low level operational waste goes to landfills at the power plants, or at Studsvik. Decommissioning waste will in principle be handled the same way as the operational waste, once the decommissioning starts and that SFR is extended to store also decommissioning waste. A small amount of waste also gomes from industri, research and medical care, but all this waste is reprocessed at Studsvik before coming to our facilities.
Långlivat och kortlivat från driften som går till mellanlagring eller slutförvaring. Samma för rivningen där avfallsströmmarna går likadant. Sedan från industri, forskning och sjukvård. Dessutom “land-fills” vid kraftverken och Studsvik.
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3. Waste volumes Decommissioning waste ca 90 000 m3 Spent fuel
( )
Spent fuel
ca m3
Long-
lived LILW
ca m3
Operational waste
ca m3
This gives a rough picture of the total waste volumes expected from the present Swedish nuclear program. For comparison it is placed in the sports arena, surprisingly named the Globe, in Stockholm. The decommissioning waste may be significantly smaller depending on the possibilities for free release and availability of landfills.
Avfallsmängd som deponeras under mark om dagens 10 reaktorer
ges en drifttid på år:
Kortlivat driftavfall till SFR-1: m3
Kortlivat rivningsavfall till SFR ( ) m3
Långlivat låg- och medelaktivt avfall från härdkomponenter och Studsvik samt rivningsavfall från inkapsling och CLAB: m3 till SFL 3-5 (Långlivat: reaktordelar, m3 från Studsvik, resten kortlivat rivningsavfall)
Använt kärnbränsle: ton, som inkapslat har en kapselvolym på drygt m3.
Total mängd ca m3 inklusive Studsvik ( enligt bilden)
Avfallsmängd som deponeras ovan mark
I markförvar på kärnkraftverken och vid Studsvik: m3
Inaktivt avfall (friklassas) från rivning av kkv: ton
Short-lived
Long-lived
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4. Standardized Waste Packages
Steel Container
Concrete tank
Concrete mould
These are the standardized waste packages we use. 200 litre’s steel drums, steel and concrete cubicles roughly 1,7 cubic metres, concrete tanks for dewatered ion exchange resins, and steel tanks (so called BFA-tanks) for long-lived waste, mainly core components, and finally standard 20 foot containers for the low level waste.
De olika avfallsbehållarna. BFA-tankarna för härdkomponenter finns inte med på bilden.
Steel mould
Steel Drums
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5. Waste Categorization System - Example
Radioactivity
Content of long-lived radionuclides
High activity
Intermediate activity
Low activity
Short-lived
Long-lived
Needs cooling and shielding
Heat effect approximately
2 kW/m3
Needs shielding but no cooling
Surface doserate
> 2 mSv/h
Needs no cooling or shielding
< 2 mSv/h
Dominating content of radionuclides with a half-life T1/2 < 31 year
Significant content of radionuclides with a half-life T1/2 >31 year
This is the overall categorisation of the radioactive waste. It’s divided depending on the level of radioactivity and on the half-life of the nuclides. High radioactivity, that needs both cooling and shielding. Intermediate level radioactivity, that needs shielding but no cooling, and low activity, that need neither shielding nor cooling. Then we also have a split in short-lived and long-lived nuclides, with the limit less than thirty one years for short-lived nuclides.
Indelningen av avfallet för att styra det till rätt avfallskategori och slutförvar.
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6. Typical final handling of waste
High activity
Half-life
Short-lived
Long-lived
Type of waste
Geologic disposal - KBS-3 concept
Spent nuclear fuel
Core components – reactor internals
Waste from research
Geologic disposal - SFL
Geologic disposal - SFR
Operational waste,
decommissioning waste
This is an other way of presenting the how the waste is handled. From low to high activity we have a split of the waste between different storage sites. From free release, via landfills, short-lived waste to long-lived waste up to storage of spent fuel in the KBS3-concept.
Ett annat sätt att visa hur avfallet styrs.
Surface repository
(Landfill)
Free released material
Free released material
Low activity
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7. SFR – Final Repository for LILW (at Forsmark NPP, commissioned in 1988)
Regional workshop WAC Lithuania —11-11

8. SFR
This shows the SFR repository with the 4 rock caverns and the silo. Low level waste in containers in the BLA cavern, 2 caverns for concrete tanks and ash drums. Intermediate level waste in the Silo and in BMA, both with concrete compartment structures.
Vi ska hålla SFR I trim många år framåt (2075?) och vi skall säkerställa att vi kan uppfylla det initialtillstånd som förutsätts i säkerhetsanalyserna.
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9. This shows the concrete structure of BMA, for intermediate level waste, in SFR. Considering the long-term safety, this gives us some interesting requirements on the waste and the repository. For spent fuel the main safety function is confinement; that is, complete isolation of the waste, e.g. with copper canisters as in the KBS-3 concept. But for low and intermediate level waste the safety functions are quite different. The main safety functions are it is limits on the amount of radioactivity and delay of the transport of the nuclides to the biosphere. So we need to consider the type of waste, half-life of the nuclides, and transport properties of the nuclides. This gives us two (2) main requirements; the waste package must not harm the repository structure, and the “environment” should not harm the repository structure. Thus, for short-lived waste the main “effort” is on the waste package, and for long-lived waste, also the waste package, but also more importance must be placed on the repository design, including the engineered barriers and location of the repository. In the short term, the waste package must not swell and break the repository structure, and in the long term, still the waste package must of course not swell, but also not leach materials that degrade the concrete structure. Also the concrete structure it self must not contain material that in these long time frame significantly degrades the structure, and surrounding groundwater and groundwater salts should not seriously degrade the structure.
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10. Här är en intressant fråga: Skall vi kringgjuta runt bitumenfat
Här är en intressant fråga: Skall vi kringgjuta runt bitumenfat? Gör en svällning så att betongstrukturen spräcks? Kringgjutning sker i Silon men i nuläget inte i BMA.
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11. Waste categories in different parts of SFR 1 facility
Till detta kommer BFA-tankar, dvs ståltankar (50, 100, 150, 200 mm stålplåt) med betongtanksmått, för härdkomponenter, och bl. a. Berglöfslådor för allmänt skrot(?).
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12. Decommissioning waste
Final disposal of decommissioning waste at final repository for operational waste.
The final repository for operational waste will be more than double in size.
Will be in operation 2020: application in the end of 2013 and start of con-sturction around 2016.
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13. We are presently working with a license application for the extension of SFR to store also decommissioning waste. The new area will contain a rock cavern for intermediate level waste where also operational waste will be stored. Further, it will contain space for storage of whole BWR-reactor pressure vessels, and space for interim storage of long-lived intermediate level waste, mainly core components. We are also starting work with the design of a repository for long-lived waste, called the SFL. This may be below SFR, possibly close to the spent fuel repository or at some other site.
Notera placeringen av BMA jämfört med BLA-förvaren I den nya delen. I den gamla ligger BMA nedströms BLA och vi riskerar att diverse komplexbildare från BLA kan strömma genom BMA. Ev. läggs BMA på västsidan av påfartstunnlarna.
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14. For handling of core components we have a brand new equipment which this year has been taken into operation at the Forsmark site. Here comes some pictures of this handling equipment.
Storage rack for the core components.
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15. Wet hood for radiation shielding
Wet hood for radiation shielding. We can see that the lid of the wet shield is lowered through the hood and is gripping the waste store rack below.
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16. Now the waste rack is transferred to the Dry shield where it is placed in the steel storage container, the so called “BFA-tank”, inside the transport container. We then have a system for drying the waste before the lid is placed on the tank. The thickness on the steel tanks is 5, 10, 15 or 20 mm, depending on the radiation level.
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17. Thereafter the core component BFA-tank is taken into interim storage at the site. This is from the Forsmark NPP. The final repository for long-lived radioactive waste, mainly core components, is presently planned to be in operation in 2045.
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18. Industry guideline for Low- and Intermediate level waste
Industry guideline established 2004
Before 2004 an authority document
Content:
Guideline for description and assessment of waste for final disposal
Waste acceptance criteria
Disposition of waste type description
Disposition of verification of waste acceptance criteria
Specific waste acceptance criteria för SFR
Specific storage rules for waste packages in SFR
Code system for waste packages, waste and conditioning methods
Regional workshop WAC Lithuania —11-11

19. Waste Acceptance Criteria (WAC) & Waste Type Descriptions (WTD)
Defines the waste properties allowed in order to comply with safety assessment and environmental assessment of the disposal facility
WAC are also identified for the production, interim storage and transportation for waste packages
WTD
Is a standardized description of a certain waste type to check compliance with the defined WAC in all relevant handling steps
Waste Package Data
Data for each waste package is checked for compliance with approved WTD (and thereby WAC) prior to permission to ship for disposal
Regional workshop WAC Lithuania —11-11

20. Methodology for WAC in Sweden
Producers are responsible for describing waste package specification – reported in a waste type description
Waste type description (WTD) includes all the steps from production of the waste to final storage for LILW
WAC concerning safety, technology and formal aspects are included in the waste type description
SKB are verifying all WAC described in a WTD in a specific review paper
Regional workshop WAC Lithuania —11-11

21. WAC for non-heat generating waste
Waste type description
For a defined waste stream
Described in 5 handling steps:
Production
Interim storage
Transport
Handling in final repository
Final storage
WAC specifies requirements in these areas:
General
Radiological
Chemical
Mechanical QC
Waste package
References
Inventory
Volume
Material
Radionuclides
Nuclear facility
Waste streams
E.g. ion exchange resins
Scrap metal
Rubble
Classification of waste
Short-lived
Long-lived
Free release
VLLW
LLW
ILW
LILW
Review process
Combined evaluation on
Production, Transportation and Final repository
Type of waste decides the final route
Regional workshop WAC Lithuania —11-11

22. WAC for non-heat generating waste - continued
Input data
Inventory from waste types
Repository design e.g. SFR
Models for:
- Near-field
- Far-field
- Biosphere
Safety assessment
FEP:s evaluated
Scenarios evaluated
Risc criteria 10-6
Calculations
Safety report
Producer
Transport system
Final repository
”WAC derivation is in practice an iterative process that deals with waste streams described in a waste type description that is evaluated quantitative and qualitative in a safety
assessment for a repository, regarding to relevant input data with specific criteria for risc or dose to be calculated” . The method for determining the WAC should continuously be re-evaluated.
Specific WAC can be described qualitatively and/or quantitatively for a fixed system,
but will then be unique for that system. If there is a lack of detailed criterias, the WAC could only be generically expressed.
Regional workshop WAC Lithuania —11-11