Requirements and Concepts for Waste Containers for Heat-Generating Radioactive Waste and Spent Fuel in Rock Salt, Claystone, and Crystalline Rock
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Requirements and Concepts for Waste Containers for
Heat-Generating Radioactive Waste and Spent Fuel in
©2021 BGE TECHNOLOGY GmbH
Rock Salt, Claystone, and Crystalline Rock
Wilhelm Bollingerfehr, Ansgar Wunderlich (BGE TECHNOLOGY GmbH)
Sabine Prignitz (BGE Bundesgesellschaft für Endlagerung mbH)
Holger Völzke, Christian Herold, Dietmar Wolff (Bundesanstalt für Materialforschung und –prüfung)
WMSymposia2021 | Wilhelm Bollingerfehr et. al.
Context
German Site Selection Act (StandAG) as of summer 2017:
Repository systems for 3 host rock formations to be considered
©2021 BGE TECHNOLOGY GmbH
Rock salt, claystone and crystalline rock
Type and total amount of expected heat generating waste:
Waste from reprocessing: approx. 8000 coquilles
Spent nuclear fuel: approx. 10,500 t of HM
Waste container considered as a pivotal barrier of the entire repository system
Question:
How to correctly derive requirements for waste containers designed for HLW and SF?
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 1
Status of HLW-Waste Container Development
©2021 BGE TECHNOLOGY GmbH
POLLUX® 10 POLLUX® 3
real existing waste container idea of a waste container without any
(prototype), detailed planning
manufactured on the basis of adjusted for a repository concept in
detailed design calculations claystone
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 2
Status of HLW-Waste Container Development
©2021 BGE TECHNOLOGY GmbH
POLLUX® 10 POLLUX® 3
real existing waste container idea of a waste container without any
(prototype), detailed planning
manufactured on the basis of adjusted for a repository concept in
detailed design calculations claystone
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 3
R&D-Project KoBrA
In summer 2017 BMWi launched the R&D-Project:
„Requirements and concepts for waste containers for the disposal of heat generating
radioactive waste and spent nuclear fuel in rock salt, claystone and crystalline rock“
©2021 BGE TECHNOLOGY GmbH
(„Anforderungen und Konzepte für Behälter zur Endlagerung von Wärme
entwickelnden radioaktiven Abfällen und ausgedienten Brennelementen in Steinsalz,
Tonstein und Kristallingestein“ – Acronym: KoBrA)
Project partners:
BAM (Bundesanstalt für Materialforschung und –prüfung), Berlin and
BGE TECHNOLOGY GmbH, Peine (coordinator)
Project duration: July 2017 to April 2020
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 4
Work Program
1. Survey of international existing requirements and concepts for waste container
©2021 BGE TECHNOLOGY GmbH
2. Identification of waste container-relevant boundary conditions and load parameter
3. Derivation and compilation of requirements for waste containers
4. Development of ideas and concepts for waste container designs
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 5
Waste Container Worldwide
Host rock Container concept (Developers) Description Status of development
well advanced in the licensing
KBS-3 unshielded double-hull cask (cast-iron cask with solid procedure (tests for production,
(SKB/Posiva Oy, Sweden, Finland) copper cladding) for fuel assemblies loading, sealing, transport,
©2021 BGE TECHNOLOGY GmbH
storage)
concept study derived from KBS-
Crystalline Rock UOS unshielded double-hull cask made of different steels for fuel
3
(Škoda, Czech Rep.) assemblies
("KBS-3 made of steel")
UFC II unshielded steel container with thin copper coating for advanced concept (material,
(NWMO, Canada) (CANDU) fuel assemblies production and container tests)
Category C Container advanced concept (material,
unshielded steel canisters or fuel assemblies
(Andra, France) production and container tests)
Supercontainer steel cask for fuel assemblies or HLW canisters enclosed in
Claystone Material tests
(ONDRAF/NIRAS, Belgium) concrete
generic design for fuel
assemblies and canisters
Reference container unshielded, robust steel container for fuel assemblies or
considered by RWM as a
(Nagra, Switzerland) HLW canisters
possible reference concept for
final disposal containers in salt
BSK-3 Concept developed in R&D
unshielded steel canisters for the borehole storage of drawn
Rock salt reports; emplace-ment
(GNS, Germany) fuel rods or HLW canisters
technology tested on dummy
POLLUX®-10 advanced concept (POLLUX®-8
shielded double-hull cask (steel and cast iron) for drawn fuel
manufactured as prototype;
(GNS, Germany) rods or HLW canisters
storage technology tested)
Existing containers;
Transport and Storage Casks, e.g. CASTOR® shielded transport and interim storage casks made of cast
-- suitability for final disposal not yet
(GNS, Germany) iron or forged steel for fuel assemblies or HLW canisters
considered
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 6
Waste Container Boundary Conditions
2. concepts for a repository in claystone
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1. concept for a repository in rocksalt
German French
Repository Concept Repository Concept
(R&D-Project: AnSicht) (Source: Andra)
Source: SKB
3. concept for a repository in
crystalline rock
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 7
Waste Container Boundary Conditions
2. concepts for a repository in claystone
©2021 BGE TECHNOLOGY GmbH
1. concept for a repository in rocksalt
But how to derive correctly a comprehensive set of requirements
for waste containers for different host rocks?
German French
Repository Concept Repository Concept
(R&D-Project: AnSicht) (Source: Andra)
Source: SKB
3. concept for a repository in
crystalline rock
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 8
Methodological Approach
©2021 BGE TECHNOLOGY GmbH
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 9Methodological Approach
©2021 BGE TECHNOLOGY GmbH
The idea is to:
• Start with a compilation of requirements (regulatory, etc.)
• Consider the lifecycle of the waste containers,
• Derive container functions
• Analyse and compile the possible loads, effects, and processes
• Eventually create generic concepts
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 10Methodological Approach
©2021 BGE TECHNOLOGY GmbH
• Siting process in Germany = a stepwise approach
• Derivation of container requirements as well
First general, than host rock specific, eventually site specific
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 11Fundamental Container Requirements
Six fundamental requirements, all of them initially independent of the host rock:
©2021 BGE TECHNOLOGY GmbH
Confinement of the radioactive inventory,
Shielding of ionising radiation,
Exclusion of criticality,
Temperature limitation of the waste container,
Limitation of corrosion and gas production,
Handleability
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 12Phases of a Repository Life Time
Phase 1:
Emplacement phase (provision of the container for emplacement until emplacement of
©2021 BGE TECHNOLOGY GmbH
the container is completed)
Phase 2:
Retrievability phase (completion of emplacement of the container until start of
decommissioning of the repository)
Phase 3:
Recoverability phase (start of decommissioning of the repository until 500 years after
closure of the repository)
Phase 4:
Later post-operational phase (500 years after closure of the repository until the end of
the reference period)
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 13Basic Container Requirements (e.g. for crystalline rock)
Time phase
Basic Requirement
Emplacement Retrievability Recovery Later post-operation
To be sufficiently ensured for Requirements depend on CRZ
Containment of the
©2021 BGE TECHNOLOGY GmbH
To be fully ensured developments that are probable (Containment Providing Rock
radioactive inventory or can be expected Zone)
To be sufficiently ensured for
To be sufficiently ensured for repository operation developments that are probable
Shielding of ionising
or can be expected
radiation
To be sufficiently ensured to avoid radiologically- or radiolytically-induced damage to further barriers
Exclusion of criticality To be fully ensured for the most reactive arrangement of the nuclear fuel
To be sufficiently ensured for
Temperature limitation To be sufficiently ensured for repository operation developments that are probable
or can be expected
Limitation of corrosion To be sufficiently ensured to prevent unacceptable corrosion
and gas production in case of contact with the hydro-chemical environment
To be sufficiently ensured for
Handleability To be sufficiently ensured developments that are probable
or can be expected
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 14Basic Container Requirements (e.g. for crystalline rock)
Time phase
Basic Requirement
Emplacement Retrievability Recovery Later post-operation
To be sufficiently ensured for Requirements depend on CRZ
Containment of the
©2021 BGE TECHNOLOGY GmbH
To be fully ensured developments that are probable (Containment Providing Rock
radioactive inventory or can be expected Zone)
To be sufficiently ensured for
To be sufficiently ensured for repository operation developments that are probable
Shielding of ionising
or can be expected
radiation
To be sufficiently ensured to avoid radiologically- or radiolytically-induced damage to further barriers
Exclusion of criticality To be fully ensured for the most reactive arrangement of the nuclear fuel
To be sufficiently ensured for
Temperature limitation To be sufficiently ensured for repository operation developments that are probable
or can be expected
Limitation of corrosion To be sufficiently ensured to prevent unacceptable corrosion
and gas production in case of contact with the hydro-chemical environment
To be sufficiently ensured for
Handleability To be sufficiently ensured developments that are probable
or can be expected
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 15Quantification of Function: e.g. Temperature Limitation
Type of Temperature Explanation Source
©2021 BGE TECHNOLOGY GmbH
Type B(U)
Max. 85°C for handleability
Surface Temperature shipped item ADR,
50°C on touchable surfaces
2017
Surface Temperature 100°C as preliminary surface temperature of waste container StandAG, 2017
200°C for Rock salt VSG
Surface Temperature
150°C for Claystone ANSICHT
100°C for Crystalline rock „KBS-3 Concept“
Construction
390°C for PWR-SF
Temperature of documents POLLUX®,
410°C for BWR-Sf
Inventory 1986
500°C for glass of vitrified waste
FZKA, 2001
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 16Quantification of Function: e.g. Temperature Limitation
Type of Temperature Explanation Source
©2021 BGE TECHNOLOGY GmbH
Type B(U)
Max. 85°C for handleability
Surface Temperature shipped item ADR,
50°C on touchable surfaces
2017
Surface Temperature 100°C as preliminary surface temperature of waste container StandAG, 2017
200°C for Rock salt VSG
Surface Temperature
150°C for Claystone ANSICHT
100°C for Crystalline rock „KBS-3 Concept“
Construction
390°C for PWR-SF
Temperature of documents POLLUX®,
410°C for BWR-Sf
Inventory 1986
500°C for glass of vitrified waste
FZKA, 2001
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 17Classification of Relevant Impacts on Waste Containers
Impact class Nature of the relevant impact Possible consequences
Rock pressure,
Swelling pressure, Water pressure
(isotropic, anisotropic)
©2021 BGE TECHNOLOGY GmbH
Static
Shear
Assembly; Material or component failure;
Mechanical Handling
Danger to the safety functions
Accelerations, vibrations, shocks from
handling and repository operation
Dynamic
Accident scenarios, e.g. container crash
Decay heat of radioactive waste
Thermal damage to technical,
Thermal Rock temperature
geotechnical and/or geological barriers
Accident fire
Material embrittlement / decomposition;
Radiological Gamma and neutron radiation Radiolysis gas formation
Corrosion
Corrosive media Material decomposition
Chemical and
Free water Hydrogen embrittlement
Biological
Microorganisms Stress corrosion cracking
Gas formation
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 18Classification of Relevant Impacts on Waste Containers
Impact class Nature of the relevant impact Possible consequences
Rock pressure,
Swelling pressure, Water pressure
(isotropic, anisotropic)
©2021 BGE TECHNOLOGY GmbH
Static
Shear
Assembly; Material or component failure;
Mechanical Handling
Danger to the safety functions
Accelerations, vibrations, shocks from
handling and repository operation
Dynamic
Accident scenarios, e.g. container crash
Decay heat of radioactive waste
Thermal damage to technical,
Thermal Rock temperature
geotechnical and/or geological barriers
Accident fire
Material embrittlement / decomposition;
Radiological Gamma and neutron radiation Radiolysis gas formation
Corrosion
Corrosive media Material decomposition
Chemical and
Free water Hydrogen embrittlement
Biological
Microorganisms Stress corrosion cracking
Gas formation
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 19Transferability of international Container Concepts
©2021 BGE TECHNOLOGY GmbH
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 20Transferability of international Container Concepts
©2021 BGE TECHNOLOGY GmbH
In principle transfer of concepts possible – however, national requirements prevail
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 21Solution Matrix for Container Concepts
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March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 22Solution Matrix for Container Concepts
©2021 BGE TECHNOLOGY GmbH
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 23Schematic Diagram of Generic Container Concepts
chosen technical solution for neutron shielding
without moderator material with moderator material
Material of the
cast steel cast iron cast steel cast iron
inner container
©2021 BGE TECHNOLOGY GmbH
Sketches of possible container concepts for final disposal in host rock...
crystalline rock
Without
CRZ
CRZ
with
stone
clay-
corrosion
with
rock salt
without corrosion
corrosion protection
stainless
Colour legend cast iron (cast) Steel (copper, titanium, nickel
steel
alloy)
inventory ● moderator rod (exemplary)
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 24Conclusions & Recommendations
1. Continuous monitoring of international waste container concept developments
2. Improvement of geological database for potential repository sites
©2021 BGE TECHNOLOGY GmbH
3. Concretisation of the site-specific requirements for waste container
4. Concretisation of the operation-related impacts on waste container
5. Development of decision criteria for suitable repository concepts
6. Preference: robust container concepts, proven and tested materials and technologies
7. Start of development of container concepts for claystone and crystalline rock asap
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 25Acknowledgement
KoBrA-project:
©2021 BGE TECHNOLOGY GmbH
Funded by the Federal Ministry for Economic Affairs and Energy (BMWi),
Represented by the Project Management Agency Karlsruhe,
Karlsruhe Institute of Technology (KIT)
Project results available:
Synthesis report in German and English
4 technical reports
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 26©2021 BGE TECHNOLOGY GmbH
Thank you for your attention!
March 11, 2021 WMSymposia2021|Wilhelm Bollingerfehr, et. al. 27You can also read
