Technical concepts for storing HLW - Monitoring, renewal and refurbishment of storage facilitites
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1 Technical concepts for storing HLW - Monitoring, renewal and refurbishment of storage facilitites Dipl.-Ing. Dennis Köhnke Dipl.-Ing. Manuel Reichardt Institute for Building Materials, Concrete Construction and Fire Protection Technische Universität Braunschweig 19th REFORM Group Meeting, Salzburg, 2. September 2014
2 Organisation within ENTRIA WP 7.1: Civil Engineering Concepts WP 7.2: Probabilistic, monitoring-based Safety- and Life-Cycle-Concept WP 7.3: Requirements due to Methods of Waste Treatment 2
3 Interim storage in Germany Lubmin (2039) Since 1960 s: Disposal in deep geological formations planned as the final step of radioactive waste management Ahaus (2036) Gorleben (2034) Site Selection Law (2013): Site selection for the future repository for heat-generating radioactive waste should be finished by Example for the timespan between site selection and start-up: Repository for not heat-generating radioactive waste Schacht Konrad : Start of the licensing procedures in Estimated beginning of disposal in Centralized storage facility Decentralized storage facility: WTI-Concept STEAG-Concept Tunnel-Concept 3
4 Interim storage in Germany Lubmin (2039) Since 1960 s: Disposal in deep geological formations planned as the final step of radioactive waste management Emsland (2042) Ahaus (2036) Gorleben (2034) Site Selection Law (2013): Site selection for the future repository for heat-generating radioactive waste should be finished by Example for the timespan between site selection and start-up: Repository for not heat-generating radioactive waste Schacht Konrad : Start of the licensing procedures in Estimated beginning of disposal in Centralized storage facility Decentralized storage facility: WTI-Concept STEAG-Concept Tunnel-Concept 4
5 Interim storage in Germany Brunsbüttel (2046) Emsland (2042) Ahaus (2036) Biblis (2046) Grohnde (2046) Grafenrheinfeld (2046) Gundremmingen (2046) Krümmel (2046) Gorleben (2034) Neckarwestheim (2046) Lubmin (2039) Since 1960 s: Disposal in deep geological formations planned as the final step of radioactive waste management Site Selection Law (2013): Site selection for the future repository for heat-generating radioactive waste should be finished by Example for the timespan between site selection and start-up: Repository for not heat-generating radioactive waste Schacht Konrad : Start of the licensing procedures in Estimated beginning of disposal in Centralized storage facility Decentralized storage facility: WTI-Concept STEAG-Concept Tunnel-Concept 5
6 Interim storage in Germany Brunsbüttel (2046) Unterweser (2047) Emsland (2042) Ahaus (2036) Biblis (2046) Philippsburg (2047) Brokdorf (2047) Grohnde (2046) Grafenrheinfeld (2046) Gundremmingen (2046) Krümmel (2046) Gorleben (2034) Neckarwestheim (2046) Isar (2047) Lubmin (2039) Since 1960 s: Disposal in deep geological formations planned as the final step of radioactive waste management Site Selection Law (2013): Site selection for the future repository for heat-generating radioactive waste should be finished by Example for the timespan between site selection and start-up: Repository for not heat-generating radioactive waste Schacht Konrad : Start of the licensing procedures in Estimated beginning of disposal in Centralized storage facility Decentralized storage facility: WTI-Concept STEAG-Concept Tunnel-Concept 6
7 Which requirements have to be met? IAEA Safety Standards [SF-1]: The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation Ensured by: Radiaton shielding Safe enclosure Removal of decay heat Subcriticality 7
8 Resistance of storage facilities Individual components (Building/Cask) RB,design Whole system RC,design RS,design 8
9 General storage concepts Part 1 Referring to [1], [2] Type Option Examples Independent Spent Fuel Storage Pool (Wet Storage of Spent Fuel) Vertical Dual-Purpose Spent Fuel Dry Storage/Transfer Cask Concrete Dry Storage Vault with Thimble Tube Storage Wells Water in a deep stainless steel lined concrete pool within an enclosed structure Heavily shielded steel cask with spent fuel sealed in inner steel canister (i.e. doublelidded) Heavily shielded concrete vault with thimble tube storage wells for spent fuel Most ARs + many AFRs worldwide CASTOR, TN, NAC- ST/STC, BGN Solutions MVDS, MACSTOR, HABOG Centralized wet storage facility (Oskarshamm, S) [3] Decentralized storage facility for dual -purpose casks (Krümmel, D) [4] Centralized vault storage facility HABOG (Vlissingen, NL) 9
10 General storage concepts - Part 2 Referring to [1], [2] Type Option Examples Vertical Concrete Dry Spent Fuel Storage Cask/Silo Heavily shielded concrete cask/silo with spent fuel sealed in an inner steel canister CONSTOR, HI-STORM Horizontal Modular Concrete Dry Spent Fuel Storage Dry Geologic Storage (Tunnel or Mine) Heavily shielded modular concrete storage with spent fuel sealed in an inner steel canister Dry gas-filled spent fuel canisters emplaced in an isolated deep tunnel or mine and backfilled with earth NUHOMS, NAC- MPC/UMS, MAGNASTOR HI-STORM Vertical storage cask [5] NUHOMS Horizontal storage module [6] 10
11 HABOG at Vlissingen, NL COVRA: HABOG: Centrale Organisatie voor Radioactief Afval (Central Organisation for Radioactive Waste) Hoogradioactief Afval Behandeling- en Opslag Gebouw (High Level Waste Treatment and Storage Building) 11
12 Design of the HABOG at Vlissingen, NL Storage of heat-generating/not heat-generating high level waste in different storage modules Referring to an image by COVRA 12
13 Design of the HABOG at Vlissingen, NL Model of a metal storage tube filled with canisters containing vitrified waste at the HABOG Schematic cross section through HABOG Referring to an image by COVRA 13
14 Impressions of the HABOG at Vlissingen, NL Heavy shielding door Reception Area Hot Cell Storage module for heatgenerating high level waste 14
15 STEAG-Concept at Krümmel, Germany Operator: Vattenfall [4] Construction: STEAG (Steinkohlen-Elektrizitäts-AG) 15
![Vattenfall [4]](/docs-images/41/12628399/images/page_15.jpg "Construction: STEAG")
16 reception area Schematic design of a STEAG storage facilitiy maintenance room storage area operating area Schematic design of a STEAG storage facility Referring to an image by the BfS 16
17 Schematic design of a STEAG storage facilitiy Schematic cross section through a STEAG storage facility Referring to an image in atw (2000) 17
18 Impressions of the STEAG-facility at Krümmel Reception area Storage area Heavy shielding door Maintenance room 18
19 How are the safety objectives realized? Safety objectives in general: Radiaton shielding Safe enclosure Removal of decay heat Subcriticality Specified in (inter-)national guidelines, e.g.: IAEA-TECDOC Selection of Away- From-Reactor Facilities for Spent Fuel Storage - A Guidebook ESK (D) - Guidelines for dry cask storage of spent fuel and heat-generating waste ENSI-G04/d (CH) - Design and operation of storage facilities for radioactive waste and spent fuel 19
20 IAEA-TECDOC A Guidebook [1] PROJECT NEEDS AND SELECTION CRITERIA FOR AFR STORAGE 1. Spent fuel information 2. Location and infrastructure 3. Facility needs 4. Resourcing needs 5. Regulatory needs 6. Management of project, quality and risk 7. International obligations 8. Site 9. Safety and licensing 10. Environmental impact 11. System flexibility 12. Operation and maintenance 13. Decommissioning 14. Cost and financing 15. Bid evaluation Project needs Selection criteria 20
21 IAEA-TECDOC Safety and licensing [1] Structural performance Ability to withstand loads and to last for the required period Compatible with site and environmental conditions Ability to withstand accident conditions Potential for massive collapse of structures and their impact on safety should be known Heat removal Temperature limits should be established Adequate heat removal required Subcriticality Inadvertent criticality should not be possible Neutron absorbing material if used should last for the life of the facility All credible situations affecting criticality safety should be reviewed. Shielding Adequate shielding Appropriate measures to prevent loss of shielding Storage should maintain its shielding for all fuel handling activities Occupational and off-site doses should be acceptable 21
22 IAEA-TECDOC Safety and licensing [1] Structural performance Ability to withstand loads and to last for the required period Compatible with site and environmental conditions Ability to withstand accident conditions Potential for massive collapse of structures and their impact on safety should be known Heat removal Temperature limits should be established Adequate heat removal required Subcriticality Inadvertent criticality should not be possible Neutron absorbing material if used should last for the life of the facility All credible situations affecting criticality safety should be reviewed. Shielding Adequate shielding Appropriate measures to prevent loss of shielding Storage should maintain its shielding for all fuel handling activities Occupational and off-site doses should be acceptable 22
23 How are the safety objectives realized? Heat removal Air outlet Air inlet Schematic cross section through a STEAG storage facility Referring to an image in atw (2000) 23
24 How are the safety objectives realized? Heat removal Air outlet Air inlet Schematic cross section through HABOG Referring to an image by COVRA 24
25 IAEA-TECDOC Safety and licensing [1] Structural performance Ability to withstand loads and to last for the required period Compatible with site and environmental conditions Ability to withstand accident conditions Potential for massive collapse of structures and their impact on safety should be known Heat removal Temperature limits should be established Adequate heat removal required Subcriticality Inadvertent criticality should not be possible Neutron absorbing material if used should last for the life of the facility All credible situations affecting criticality safety should be reviewed. Shielding Adequate shielding Appropriate measures to prevent loss of shielding Storage should maintain its shielding for all fuel handling activities Occupational and off-site doses should be acceptable 25
26 Structural performance - Action and resistance Action A Resistance R A A A R (t) R average life A (t) time t p f Probability of failure reliability Z technical life z z Refering to: [11] 26
27 Scattering of material (concrete) parameters Inside concrete by Micro-CT 27
28 Why does the resistance of a structure decrease? Several parameters related to: material structural details or design workmanship internal stresses external stresses in-service stresses level of maintenance. [10] 28
29 state State-lifetime-relation of a building with respect to extreme actions planned action Residual resistance Storage facility extreme action Partial- or total damage extreme action permanent, planned action residual resistance ultimate limit state lifetime 29
30 Monitoring methods [Source: 12] 30
31 reception area Monitoring and refurbishment in the storage area? maintenance room storage area operating area Schematic design of a STEAG storage facility Referring to an image by the BfS 31
32 Thank you for your attention! Project number 02S9082A 32
33 References [1] International Atomic Energy Agency: IAEA-TecDoc-1558: Selection of Away-From-Reactor Facilities for Spent Fuel Storage - A Guidebook, September 2007 [2] National Nuclear Security Administration, Office of Nonproliferation and International Security (NIS): Next Generation Safeguards Initiative. Safeguards-By-Design Facility Guidance Series (NGSI-SBD-001). Guidance for Independent Spent Fuel Dry Storage Installations. May 2012 [3] [4] %20%20%20%20%20%20%20%20%20%20%20&Mode=download [5] [6] Photograph by Vattenfall [7] Complementary Safety margin Assessment COVRA N.V. (HABOG) [8] Statement of the Nuclear Waste Management Commission (ESK) ESK stress test for nuclear fuel cycle facilities in Germany. Part 1: Nuclear fuel supply facilities, storage facilities for spent fuel and heat-generating radioactive waste, facilities for the treatment of spent fuel [9] [10] Service life management system of concrete structures in nuclear power plants - Erkki Vesikari - ESPOO 2007 VTT Publications 648 [11] Gehlen, Christoph: Probabilistische Lebensdauerbemessung von Stahlbetonbauwerken Zuverlässigkeitsbetrachtungen zur wirksamen Vermeidung von Bewehrungskorrosion, DAfStb (2000), Heft 510. [12] Assessment and management of ageing of major nuclear power plant components important to safety: Concrete containment buildings - IAEA-TECDOC-1025, Vienna,
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