Waste Form and Packaging Process Report for the Safety Assessment SR-PSU

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Waste Form and Packaging Process Report for the Safety Assessment SR-PSU Kapitel 1 Inledning Kapitel 2 Toppdokument Förläggningsplats Ansökan om tillstånd enligt Kärntekniklagen Kapitel 3 för utbyggnad och fortsatt drift av SFR Konstruktionsregler Tolkning och tillämpning av krav i SSMFS Bilaga Begrepp och definitioner Principer och metodik för säkerhetsklassning – Projekt Begrepp och definitioner för ansökan om SFR utbyggnad utbyggnad och fortsatt drift av SFR Säkerhetsklassning för projekt SFR-utbyggnad Acceptanskriterier för avfall, PSU Kapitel 4 Anläggningens drift Allmän del 1 Kapitel 5 Anläggningsutformning Anläggnings- och funktionsbeskrivning och drift Preliminär plan för fysiskt skydd för utbyggt SFR SFR Förslutningsplan Metod och strategi för informations- och IT-säkerhet, PSU Kapitel 6 Radioaktiva ämnen Radionuclide inventory for application of extension of the SFR repository - Treatment of uncertainties. (1) (2) Låg- och medelaktivt avfall i SFR. Referensinventarium för avfall 2013 (uppdaterad 2015-03) Kapitel 7 Strålskydd Bilaga F-PSAR SFR Dosprognos vid drift av utbyggt SFR Första preliminär Kapitel 8 säkerhetsredovisning Säkerhetsanalys för driftskedet för ett utbyggt SFR SFR – Säkerhetsanalys för driftskedet Kapitel 9 Mellanlagring av långlivat avfall Utgått maj 2017 Ansökansinventarium för mellanlagring av långlivat avfall i SFR Utgått maj 2017 Huvudrapport Redovisning av säkerhet efter förslutning för SFR Allmän del 2 Huvudrapport för säkerhetsanalysen SR-PSU (1) (3) Säkerhet efter förslutning FHA report Handling of future human actions in the safety assement (2) FEP report FEP report for the safety assessment Waste process report Waste process report for the safety assessment Typbeskrivningar Geosphere process report Geosphere process report for the safety assessment Preliminär typbeskrivning för hela BWR reaktortankar Barrier process report exklusive interndelar. Engineered barrier process report for the safety assessment Preliminär typbeskrivning för skrot i fyrkokill Biosphere synthesis report Biosphere synthesis report for the safety assessment Preliminär typbeskrivning Ansökan om tillstånd enligt kärntekniklagen Ansökan för härdkomponenter i Climate report ståltankar Utgått maj 2017 Climate and climate related issues for the safety assessment Model summary report Model summary report for the safety assessment Data report Bilaga AV PSU Data report for the for the safety assessment (2) Avvecklingsplan för ett utbyggt SFR Input data report Slutförvaret för kortlivat radioaktivt avfall Input data report for the safety assessment (2) (3) Initial state report Bilaga VOLS-Ansökan PSU Initial state report for the safety assessment (2) Verksamhet, organisation, ledning och styrning för utbyggnad av SFR – Radionuclide transport report Ansökans- och systemhandlingsskede Radionuclide transport and dose calculations for the safety assessment (2) Bilaga VOLS-Bygg PSU SDM-PSU Forsmark Verksamhet, organisation, ledning och styrning Site description of the SFR area at Forsmark on för utbyggnad av SFR – Tillståndsprövnings- completion of the site investigation och detaljprojekteringsskedet samt byggskedet. Samrådsredogörelse Bilaga MKB PSU Konsekvensbedömning av vattenmiljöer vid utbyggnad av SFR Miljökonsekvensbeskrivning för Ersatt juli 2016 av bilaga SFR-U K:2 utbyggnad och fortsatt drift av SFR Naturmiljöutredning inför utbyggnad av SFR, Forsmark, Östhammar kommun. Bilaga BAT Utbyggnad av SFR ur ett BAT-perspektiv Kompletteringar (1) September 2015 – Svensk version av Huvudrapport SR-PSU i allmän del 2 samt ny version (3.0) av Radionuclide inventory i allmän del 1 kapitel 6 (2) Oktober 2015 – Fem uppdaterade rapporter i allmän del 2 samt ny version (4.0) av Radionuclide inventory i allmän del 1 kapitel 6 (3) Oktober 2017 – Uppdatering av Huvudrapport SR-PSU och Input data report Technical Report TR-14-03 Waste form and packaging process report for the safety assessment SR-PSU Svensk Kärnbränslehantering AB March 2014 Svensk Kärnbränslehantering AB Swedish Nuclear Fuel and Waste Management Co Box 250, SE-101 24 Stockholm Phone +46 8 459 84 00 ISSN 1404-0344 Tänd ett lager: SKB TR-14-03 P, R eller TR. ID 1370217 Waste form and packaging process report for the safety assessment SR-PSU Svensk Kärnbränslehantering AB March 2014 A pdf version of this document can be downloaded from www.skb.se. Preface This report compiles information on processes in the waste form and packaging that are relevant for the long-term safety of the low- and intermediate level waste repository SFR in Forsmark. It forms part of the SR-PSU safety assessment, which supports SKB´s licence application to extend and continue to operate SFR. This report has been compiled and edited by Klas Källström, SKB, and Maria Lindgren, Kemakta Konsult AB. Experts have contributed to the report, as listed in Section 1.3. The report has been reviewed by Jordi Bruno, Amphos 21, Russel Alexander, Bedrock Geosciences, Luc van Loon, PSI, and Kastriot Spahiu, SKB. Stockholm, March 2014 Fredrik Vahlund Project leader SR-PSU SKB TR-14-03 3 Summary The final repository for short-lived radioactive waste (SFR) located in Forsmark, Sweden is currently being used for the final disposal of low- and intermediate-level operational waste from Swedish nuclear facilities. SKB plans to extend the repository to host waste from the decommissioning of the nuclear power plants. The SR-PSU assessment of the long-term safety (post-closure safety) of the whole repository is an important part of the application for a licence to build the extension. This process report constitutes one of the main references supporting the Main report, which summarises the long-term safety for SFR. Processes that are expected to take place in the near field of SFR in the period up to 100,000 years post-closure are systematically documented in two process reports, including an evaluation of the importance of each process within the SR-PSU and a suggestion of how the process should be handled in the SR-PSU activities. This report addresses processes related to the waste package, i.e. the waste form and packaging. The other process report for the near field treats the processes in the technical barriers in the repository. The process reports support the description of the repository long term reference evolution. This report consists of two main chapters describing the waste form processes and the packaging processes respectively. SKB TR-14-03 5 Sammanfattning Slutförvaret för kortlivat radioaktivt avfall (SFR) i Forsmark, Sverige används för närvarande för slutlig deponering av låg- och medelaktivt driftavfall från svenska kärntekniska anläggningar. SKB planerar att bygga ut förvaret för att förvara avfall från rivning av kärnkraftverken. Analysen av lång- siktig säkerhet SR-PSU (säkerhet efter förslutning) för hela förvaret är en viktig del av ansökan om att få bygga ut förvaret. Den här processrapporten utgör en av huvudreferenserna till huvudrapporten som summerar analysen av långsiktig säkerhet för SFR. Processer som förväntas ske i närzonen i SFR under 100 000 år efter förslutning dokumenteras systematiskt i två processrapporter, vilken inkluderar utvärdering av varje process betydelse och förslag om hur processen ska hanteras inom SR-PSU. Den här rapporten behandlar processer för avfalls kollin, dvs avfallsformen och emballage. Den andra processrapporten för närzonen behandlar de tekniska barriärerna i förvaret. Processrapporterna är en viktig del i underlaget för beskrivningen av förvarets referensutveckling. Rapporten är indelad i två huvudkapitel som beskriver de relevanta processerna för avfallsformen samt avfallspaketen. 6 SKB TR-14-03 Contents 1 Introduction 9 1.1 Background 9 1.2 Report hierarchy in the SR-PSU safety assessment 10 1.3 This report 10 1.4 Identification and description of processes 12 1.4.1 Identification of processes 12 1.4.2 Structure for process descriptions 13 1.4.3 Participating experts 15 2 Definition of system components 17 2.1 Waste form 17 2.1.1 Initial state of the waste form 18 2.1.2 Definition of waste form variables 18 2.2 Steel and concrete packaging 19 2.2.1 Initial state of the packaging 20 2.2.2 Definition of the steel and concrete packaging variables 20 3 Waste form processes 21 3.1 Radiation related processes 21 3.1.1 Radioactive decay 21 3.1.2 Radiation attenuation/heat generation 23 3.1.3 Radiolytic decomposition of organic material 24 3.1.4 Water radiolysis 31 3.2 Thermal processes 34 3.2.1 Heat transport 34 3.2.2 Phase changes/freezing 36 3.3 Hydraulic processes 40 3.3.1 Water uptake and transport during unsaturated conditions 40 3.3.2 Water transport under saturated conditions 46 3.4 Mechanical processes 51 3.4.1 Fracturing 51 3.5 Chemical processes 56 3.5.1 Advective transport of dissolved species 56 3.5.2 Diffusive transport of dissolved species 62 3.5.3 Sorption/uptake 70 3.5.4 Colloid formation and transport 93 3.5.5 Dissolution, precipitation and recrystallisation 101 3.5.6 Degradation of organic materials 115 3.5.7 Water uptake/swelling 131 3.5.8 Microbial processes 137 3.5.9 Metal corrosion 147 3.5.10 Gas formation and transport 155 3.6 Radionuclide transport 163 3.6.1 Speciation of radionuclides 163 3.6.2 Transport of radionuclides in the water phase 167 3.6.3 Transport of radionuclides in the gas phase 171 4 Steel and concrete packaging 175 4.1 Thermal processes 175 4.1.1 Heat transport 175 4.1.2 Phase changes/freezing 175 4.2 Hydraulic processes 176 4.2.1 Water uptake and transport during unsaturated conditions 176 4.2.2 Water transport under saturated conditions 179 4.3 Mechanical processes 182 4.3.1 Fracturing/deformation
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