# WIA-ENE-026 PHASE-2: Storage & Containment ☢️ > **弘益人間** - Engineering robust containment for multi-generational protection ## Document Information - **Phase**: 2 of 4 - **Title**: Storage & Containment - **Version**: 1.0.0 - **Status**: Active - **Timeline**: Months 7-18 - **Dependencies**: PHASE-1 (Foundation & Classification) ## Table of Contents 1. [Introduction](#introduction) 2. [Multi-Barrier Containment Philosophy](#multi-barrier-containment-philosophy) 3. [Interim Storage Systems](#interim-storage-systems) 4. [Dry Cask Storage](#dry-cask-storage) 5. [Geological Repository Design](#geological-repository-design) 6. [Engineered Barrier Systems](#engineered-barrier-systems) 7. [Natural Barrier Systems](#natural-barrier-systems) 8. [Storage Facility Operations](#storage-facility-operations) 9. [Safety Assessment](#safety-assessment) 10. [Implementation Roadmap](#implementation-roadmap) --- ## 1. Introduction ### 1.1 Purpose Phase 2 focuses on the physical infrastructure and engineered systems required for safe storage and ultimate disposal of radioactive waste. This phase translates the classification framework from Phase 1 into concrete storage solutions ranging from interim facilities to permanent geological repositories. ### 1.2 Scope This phase covers: - Design principles for storage and disposal facilities - Multi-barrier containment system specifications - Interim storage for operational waste - Dry cask storage for spent fuel - Deep geological repository concepts - Facility siting and characterization - Performance assessment methodologies ### 1.3 Key Objectives **Month 7-9: Interim Storage Facilities** - Design near-surface storage for LLW/ILW - Specify container requirements - Plan facility layout and logistics - Begin site preparation **Month 10-12: Dry Cask Storage Systems** - Select cask designs for spent fuel - Prepare Independent Spent Fuel Storage Installation (ISFSI) - Establish loading procedures - Commission monitoring systems **Month 13-15: Geological Repository Planning** - Identify potential repository sites - Conduct geological surveys - Design repository layout - Plan URL (Underground Research Laboratory) **Month 16-18: Safety Assessment** - Perform safety analysis reports - Model long-term performance - Establish closure plans - Obtain regulatory approvals --- ## 2. Multi-Barrier Containment Philosophy ### 2.1 Defense-in-Depth Concept The multi-barrier approach provides redundant layers of protection: **Barrier 1: Waste Form** - Immobilization matrix (glass, cement, metal) - Low solubility and leachability - Chemical and physical stability - Resistant to degradation **Barrier 2: Waste Container** - Corrosion-resistant materials - Structural integrity - Sealed to prevent water intrusion - Multiple closure systems **Barrier 3: Buffer Material** - Bentonite clay or concrete - Absorbs water and limits flow - Swells to seal gaps - Provides additional shielding **Barrier 4: Backfill and Repository** - Crushed salt, concrete, or clay - Fills void spaces in repository - Limits water movement - Provides structural support **Barrier 5: Geological Formation** - Thick, stable rock formation - Low permeability - Favorable geochemistry - Isolated from human activities ### 2.2 Time Scales for Containment **Operational Period (0-100 years):** - Active monitoring and control - Retrievability maintained - Institutional controls in place - Human intervention available **Post-Closure Period (100-10,000 years):** - Passive safety systems dominant - Engineered barriers degrading - Natural barriers primary protection - No human intervention assumed **Long-Term Isolation (10,000+ years):** - Complete reliance on geological barriers - Waste form may be degraded - Radionuclides significantly decayed - Slow release to biosphere acceptable ### 2.3 Performance Objectives **Containment Goals:** - Zero release during operational period - Radionuclide flux < 0.1 mSv/year to most exposed individual - Groundwater protection to drinking water standards - Negligible ecosystem impacts **Safety Margins:** - Conservative assumptions in modeling - Multiple independent safety functions - Graceful degradation (no cliff-edge effects) - Robustness to uncertainty --- ## 3. Interim Storage Systems ### 3.1 Near-Surface Storage for LLW #### 3.1.1 Engineered Trenches **Design Features:** - Excavated trenches 5-10 meters deep - Concrete vaults or engineered liners - Layered waste packages with sand/gravel - Drainage systems to manage water **Capacity:** - Typical trench: 1,000-5,000 m³ - Facility: 50,000-500,000 m³ total - Expandable by adding trenches **Closure:** - Multi-layer cover system - Clay cap for water infiltration control - Topsoil and vegetation - Institutional controls for 100-300 years #### 3.1.2 Concrete Vaults **Structure:** - Reinforced concrete modules - Above or below grade installation - Multiple cells for waste segregation - Access corridors for emplacement **Advantages:** - Superior structural stability - Better containment than trenches - Easier monitoring - Longer design life (300+ years) **Disadvantages:** - Higher construction cost - Limited capacity per module - Complex drainage requirements ### 3.2 Intermediate-Depth Storage for ILW **Depth Range:** 50-150 meters **Geology:** - Stable sedimentary or crystalline rock - Low permeability - Minimal groundwater flow - No mineral resources **Repository Design:** - Tunnel and chamber excavation - Concrete or bentonite buffer - Waste packages in engineered alcoves - Backfilled and sealed at closure **Example: SFR Sweden** - Located beneath Baltic Sea - 50 meters below seafloor - 1 Silo for ILW (6,000 m³) - 4 Rock vaults for LLW (63,000 m³) - Operational since 1988 ### 3.3 Wet Storage for Spent Fuel **Spent Fuel Pool Design:** **Structure:** - Stainless steel-lined concrete basin - Water depth: 10-15 meters - High-density storage racks (borated stainless steel) - Redundant cooling and cleanup systems **Functions:** - Radiation shielding (water) - Decay heat removal (cooling systems) - Criticality control (borated water, rack spacing) - Contamination control (water chemistry) **Cooling Requirements:** ``` Q(t) = Q₀ × (t + t₀)^(-0.2) Where: - Q(t) = Decay heat at time t (watts) - Q₀ = Reference power - t₀ = Operating time (days) - t = Time after shutdown (days) Example: 1000 MWe reactor, 3-year fuel cycle - At shutdown: ~200 MW thermal - After 1 day: ~20 MW - After 1 month: ~6 MW - After 1 year: ~2 MW - After 5 years: ~0.6 MW - After 10 years: ~0.3 MW ``` **Water Chemistry:** - pH: 5.0-7.5 (typically ~5.5 for PWR) - Conductivity: < 1 μS/cm - Boron: 2,000-2,500 ppm (if credited for criticality) - Chemistry control to minimize corrosion **Advantages:** - Proven technology (60+ years) - Excellent shielding - Efficient heat removal - Allows fuel inspection **Disadvantages:** - Requires active systems (power, cooling) - Potential for leaks - Limited capacity - Not suitable for long-term (>50 years) --- ## 4. Dry Cask Storage ### 4.1 Dry Cask Technology **Concept:** After 5-10 years of wet storage, spent fuel can be transferred to dry casks: - Decay heat reduced sufficiently for passive air cooling - Sealed in inert atmosphere (helium) - No active systems required - Design life: 50-100+ years ### 4.2 Cask Types #### 4.2.1 Metal Casks **Design:** - Forged steel or ductile cast iron body (15-40 cm thick) - Welded or bolted lid with seals - Internal basket (stainless steel or aluminum) - Finned or smooth external surface **Examples:** - NAC-MPC: 26 or 37 PWR assemblies - TN-32: 32 PWR assemblies - HI-STORM: 24 or 32 PWR assemblies **Advantages:** - Robust mechanical protection - Good heat conduction - Can be transportable - Resistant to external hazards #### 4.2.2 Concrete Casks **Design:** - Steel canister inside concrete overpack - Concrete provides shielding (γ, n) - Canister provides containment (welded) - Vertical or horizontal orientation **Examples:** - NUHOMS: Horizontal storage modules - HI-STORM: Vertical concrete overpacks - NAC-UMS: Universal storage system **Advantages:** - Lower cost than all-metal - Excellent shielding - Passive cooling (natural convection) - High capacity per unit #### 4.2.3 Dual-Purpose Canisters **Multi-Purpose Canister (MPC) Concept:** - Single canister for storage, transport, and disposal - Eliminates repackaging (reduces exposure) - Welded stainless steel (typically 12-16 mm) - Helium backfill for heat transfer and inert atmosphere **Design Considerations:** - Must meet storage regulations (10 CFR 72) - Must meet transport regulations (10 CFR 71) - Must be compatible with disposal concepts - Structural, thermal, shielding, criticality safety ### 4.3 ISFSI Design **Independent Spent Fuel Storage Installation Layout:** **Components:** - Concrete storage pads (reinforced, seismic design) - Perimeter fence and security systems - Environmental monitoring stations - Access roads and handling equipment - Lightning protection - Drainage systems **Configuration Options:** **Vertical:** - Casks stand upright on pad - Natural convection cooling - Inlet vents at bottom, outlet at top - Compact footprint **Horizontal:** - Modules embedded in hillside or berm - Canisters inserted horizontally - Natural convection through module - Earthquake resistance **Capacity Planning:** ``` Number of casks = (Total fuel assemblies) / (Assemblies per cask) Example: 40-year reactor operation - PWR: ~1,600 assemblies generated - Assemblies per cask: 32 - Casks required: 50 - Pad area: 50 casks × 25 m² = 1,250 m² ``` ### 4.4 Loading Operations **Process Steps:** 1. **Fuel Selection:** - Minimum 5-year cooling in pool - Inspect for damage - Verify burnup and enrichment 2. **Canister Preparation:** - Install in transfer cask - Lower into pool - Remove lid underwater 3. **Fuel Loading:** - Load assemblies in specified pattern - Maintain criticality safety (spacing) - Verify correct assemblies loaded 4. **Drying and Backfill:** - Replace water with forced helium flow - Vacuum drying to remove moisture (critical!) - Backfill with helium to ~4 bar 5. **Welding and Testing:** - Weld lid (automated or manual) - Helium leak test - Pressure test 6. **Transfer to Storage:** - Move to ISFSI - Emplace on pad or in module - Install monitoring equipment **Quality Assurance:** - Pre-job briefings and procedures - Real-time monitoring of operations - Independent verification - Documentation at each step ### 4.5 Monitoring and Maintenance **Surveillance:** - Visual inspections (annual or periodic) - Radiation surveys around casks - Contamination surveys - Seal and pressure monitoring - Concrete degradation assessment **Aging Management:** - Corrosion monitoring programs - Concrete cracking inspections - Seal replacement if needed - Canister integrity verification **Maintenance:** - Repaint metal surfaces - Repair concrete spalling - Clear debris from air vents - Vegetation control --- ## 5. Geological Repository Design ### 5.1 Site Selection Criteria **Geological Factors:** - Stable, low-permeability rock (granite, clay, salt) - Depth: 300-1,000 meters - Minimal fracturing and faulting - Low groundwater flow - Favorable geochemistry (reducing conditions) - No economically valuable minerals - Seismically stable region **Geographic Factors:** - Remote from population centers (>10 km) - Adequate buffer zone - Accessible for construction and operations - Suitable surface facilities area - Minimal environmental sensitivity **Institutional Factors:** - Community acceptance - Regulatory approval feasible - Land ownership and control - Long-term institutional capability ### 5.2 Repository Concepts by Geology #### 5.2.1 Crystalline Rock (Granite) **Examples:** - Onkalo, Finland (gneiss/granite) - Forsmark, Sweden (granite) - FEBEX, Spain (granite) **Characteristics:** - Hard, competent rock - Low matrix permeability (fractures dominate flow) - Long-lived, stable formations - Good mechanical properties **Repository Design:** - KBS-3 concept (Swedish) - Deposition holes: 8m deep, 1.75m diameter, 6m spacing - One canister per hole - Bentonite buffer surrounds canister - Tunnels backfilled with bentonite/crushed rock **Canister:** - Copper outer shell (5 cm thick) for corrosion resistance - Cast iron insert for structural strength - 1-4 tonnes uranium per canister - Design life: 100,000+ years **Buffer:** - Bentonite clay rings and pellets - Swells when wet to fill void - Very low hydraulic conductivity (10⁻¹² m/s) - Limits canister movement #### 5.2.2 Clay/Shale **Examples:** - Boom Clay, Belgium (HADES URL) - Opalinus Clay, Switzerland (Mont Terri) - Callovo-Oxfordian, France (Bure) **Characteristics:** - Self-sealing properties - Very low permeability (10⁻¹³ to 10⁻¹⁴ m/s) - High sorption capacity for radionuclides - Plastic deformation (less brittle than granite) **Repository Design:** - Horizontal emplacement tunnels - Waste packages on floor or in alcoves - Clay naturally backfills excavation damaged zone - Minimal engineered barriers needed **Challenges:** - Lower mechanical strength (support required) - Gas generation concerns (slow diffusion) - Excavation disturbed zone management #### 5.2.3 Salt Formations **Examples:** - WIPP, USA (bedded salt) - TRU waste - Gorleben, Germany (salt dome) - under review - Asse, Germany (salt mine) - historic, issues **Characteristics:** - Extremely low permeability (no connected porosity) - Self-sealing creep closes fractures - High thermal conductivity - Soluble (requires dry conditions) **Repository Design:** - Rooms mined in salt formation - Waste packages stacked in rooms - Rooms backfilled with crushed salt - Creep closure over decades to centuries **Advantages:** - Essentially no water flow in undisturbed salt - Self-healing of fractures - Well-understood mining technology **Disadvantages:** - Risk if water intrudes (dissolution) - Retrieval difficult after creep closure - Limited sites available ### 5.3 Repository Layout **Surface Facilities:** - Waste receiving and inspection building - Canister transfer and welding hot cell - Ventilation systems for underground - Emergency response facilities - Administration and training buildings - Environmental monitoring lab **Underground Layout:** **Access:** - Shafts or ramps for personnel and equipment - Separate ventilation shaft - Emergency egress routes - Compartmentalized ventilation zones **Emplacement Area:** - Main tunnels (drifts): 5-6 m diameter - Deposition tunnels or rooms - Buffer zone around emplacement areas - Separation of waste types (HLW, ILW) **Typical Dimensions:** - Depth: 400-600 m - Total tunnel length: 20-50 km - Emplacement area: 1-3 km² - Repository footprint: 5-10 km² **Capacity:** - 60,000-100,000 tonnes heavy metal (spent fuel) - 100,000-500,000 m³ (ILW, TRU) - Operational period: 50-100 years - Closure and post-closure monitoring: 100+ years ### 5.4 Construction Sequence **Phase 1: Underground Research Laboratory (URL)** - Duration: 5-10 years - Small-scale underground facility - In situ characterization of host rock - Demonstration of construction methods - Full-scale tests of engineered barriers **Phase 2: Repository Construction** - Duration: 10-20 years (concurrent with operation) - Shaft/ramp excavation - Main tunnel development - Surface facility construction - Ventilation and utilities installation **Phase 3: Operations** - Duration: 50-100 years - Phased emplacement - Continuous monitoring - Maintenance of access and ventilation - Concurrent construction of new panels **Phase 4: Closure** - Duration: 5-10 years - Backfill all tunnels and shafts - Seal repository access - Decommission surface facilities - Transfer to institutional control --- ## 6. Engineered Barrier Systems ### 6.1 Waste Form Engineering #### 6.1.1 Vitrification (HLW) **Process:** - Mix waste with glass frit (borosilicate) - Melt at 1,100-1,200°C - Pour into stainless steel canisters - Cool and seal **Glass Properties:** - Leach rate: 10⁻⁵ to 10⁻⁷ g/m²/day - Radiation stability: Up to 10²⁵ α-decays/m³ - Thermal stability: Up to 500°C - Waste loading: 15-25 wt% **Canister:** - Stainless steel 304L or 316L - Diameter: 0.43 m (France), 0.61 m (USA) - Height: 3-4.5 m - Fill: 400-600 kg glass **Performance:** - Containment: 500-10,000 years - Radionuclide release limited by glass dissolution - Provides form for handling and disposal #### 6.1.2 Cementation (LLW, ILW) **Process:** - Mix waste with cement powder and water - Pour into drums or large containers - Cure at ambient conditions - Waste solidified in concrete matrix **Cement Types:** - Portland cement (most common) - Blast furnace slag cement - Polymeric materials for special wastes **Properties:** - Compressive strength: > 3.5 MPa - Leach rate: 10⁻³ to 10⁻⁵ g/m²/day - pH buffering (high pH limits solubility) - Low cost, proven technology **Limitations:** - Degradation in groundwater over centuries - Cracking from thermal or structural stress - Incompatibility with some waste types #### 6.1.3 Metal Encapsulation **Process:** - Encapsulate waste in lead or alloy matrix - Induction melting and casting - Provides dense, low-void waste form **Applications:** - Sealed sources - Special nuclear materials (Pu) - High-value wastes requiring extra security ### 6.2 Container Materials #### 6.2.1 Copper **Advantages:** - Thermodynamically stable in anaerobic conditions - No localized corrosion in bentonite buffer - High ductility (resists cracking) - Long archaeological precedents **Corrosion Rate:** - Anaerobic: 0.1-1 μm/year - 5 cm thickness lasts 50,000-500,000 years **Applications:** - Swedish/Finnish KBS-3 design - Outer shell on cast iron insert #### 6.2.2 Stainless Steel **Advantages:** - High strength and ductility - Well-established fabrication - Resistant to radiation damage - Lower cost than copper **Corrosion Concerns:** - Localized corrosion (pitting, crevice) - Stress corrosion cracking in chloride - General corrosion in low-pH environments **Applications:** - MPC canisters (USA) - HLW vitrification canisters - Disposal overpacks (some designs) #### 6.2.3 Carbon Steel **Advantages:** - Very high strength - Low cost - Simple fabrication **Corrosion:** - Uniform corrosion: 1-10 μm/year - 10 cm thickness provides 10,000-100,000 year life - Corrosion products may provide buffering **Applications:** - Overpack in some designs - Transportation casks - Storage casks #### 6.2.4 Titanium Alloys **Advantages:** - Excellent corrosion resistance - High strength-to-weight ratio - Resistant to chloride environments **Disadvantages:** - High cost - Difficult welding - Limited experience in nuclear applications **Potential Applications:** - Coastal or marine repositories - High-salinity groundwater sites ### 6.3 Buffer and Backfill Materials #### 6.3.1 Bentonite Clay **Properties:** - Montmorillonite mineral (swelling clay) - Low hydraulic conductivity: 10⁻¹² to 10⁻¹³ m/s - High swelling pressure: 1-15 MPa - High sorption capacity for radionuclides **Functions:** - Limits water access to canister - Self-sealing (fills gaps and fractures) - Retards radionuclide transport - Buffers canister movement **Specifications:** - Density: 1,600-2,000 kg/m³ (compacted) - Moisture content: 10-17% - Montmorillonite content: > 75% **Degradation Concerns:** - Transformation at high temperature (>100°C) - Cementation in high-pH plume (from concrete) - Erosion by flowing groundwater #### 6.3.2 Crushed Rock Backfill **Composition:** - Crushed host rock (granite, tuff, etc.) - May include bentonite admixture (10-30%) **Functions:** - Fills large void volumes in tunnels - Provides mechanical support - Enhances thermal properties **Properties:** - Hydraulic conductivity: 10⁻⁸ to 10⁻¹⁰ m/s - Compacted density: 1,800-2,200 kg/m³ #### 6.3.3 Concrete Backfill **Applications:** - Sealing plugs in shafts and drifts - Structural support in some designs - Low-level waste repositories **Properties:** - Low permeability formulations - High-strength for structural loads - Long-term durability **Concerns:** - High pH plume may affect bentonite - Cracking over long time periods - Interaction with host rock --- ## 7. Natural Barrier Systems ### 7.1 Host Rock Properties **Key Parameters:** **Hydraulic Conductivity (K):** - Granite (intact): 10⁻¹¹ to 10⁻¹³ m/s - Granite (fractured): 10⁻⁸ to 10⁻¹⁰ m/s - Clay: 10⁻¹² to 10⁻¹⁴ m/s - Salt: < 10⁻¹⁵ m/s (essentially zero) **Groundwater Chemistry:** - Salinity (TDS): Fresh (<1 g/L) to saline (>10 g/L) - pH: 7-9 typical for deep groundwater - Redox potential: Reducing conditions preferred - Colloid content: Low colloid transport preferred **Sorption (Kd):** - Measure of radionuclide retention on rock surfaces - Kd values: 0 (non-sorbing) to 10,000+ mL/g (strong sorption) - Higher Kd means slower transport **Examples:** - Cs-137: Kd = 100-10,000 (strong sorption on clay) - I-129: Kd = 0-1 (mobile) - Pu-239: Kd = 100-10,000 (sorbs strongly in reducing conditions) ### 7.2 Radionuclide Transport Mechanisms **Advection:** - Movement with flowing groundwater - Velocity = K × (hydraulic gradient) / porosity - Dominant for mobile species **Diffusion:** - Movement due to concentration gradient - Fick's Law: F = -D × (dC/dx) - Important in low-permeability media **Dispersion:** - Spreading due to heterogeneity - Characterized by dispersivity (α) **Sorption/Retardation:** - Attachment to mineral surfaces - Retardation factor: R = 1 + (ρb/n) × Kd - R > 1 slows transport **Matrix Diffusion:** - Diffusion into rock matrix from fractures - Greatly increases residence time - Important in fractured rock ### 7.3 Geochemical Barriers **Reducing Environment:** - Reduces solubility of many actinides - Pu, Np, U less mobile as +4 species - Maintained by limited oxygen penetration **pH Buffering:** - Rock minerals buffer pH - Limits extreme pH from waste or cement **Co-precipitation:** - Radionuclides incorporate into mineral phases - Effectively immobilized **Colloid Filtering:** - Rock matrix filters colloidal particles - Prevents colloid-facilitated transport --- ## 8. Storage Facility Operations ### 8.1 Operational Safety **Radiation Protection:** - ALARA program - Personal dosimetry (TLD, EPD) - Area monitoring (CAM, RAM) - Contamination control zones **Industrial Safety:** - Heavy load handling procedures - Confined space entry protocols - Fire protection systems - Emergency preparedness **Security:** - Perimeter intrusion detection - Access control - Video surveillance - Cybersecurity for monitoring systems ### 8.2 Waste Acceptance **Process:** - Shipper provides manifest and characterization data - Facility reviews against waste acceptance criteria - Receipt inspection (visual, radiation survey) - Acceptance or rejection decision - Documentation and tracking **Criteria Verification:** - Physical parameters (volume, weight) - Radiological content (activity, dose rate) - Chemical compatibility - Package condition ### 8.3 Quality Assurance Program **Elements:** - Written procedures for all operations - Personnel training and qualification - Independent verification - Document control - Audit and corrective action programs - Configuration management **Records:** - Waste characterization data - Chain of custody logs - Inspection and surveillance reports - Incident reports - Maintenance records - Regulatory submittals and approvals --- ## 9. Safety Assessment ### 9.1 Performance Assessment Methodology **Time Frames:** - Operational: 0-100 years (human control) - Post-closure: 100-10,000 years (regulatory period) - Long-term: 10,000-1,000,000 years (repository performance) **Scenarios:** - Base case (expected evolution) - Canister failure scenarios - Human intrusion (drilling, excavation) - Seismic and climatic events - Criticality (for fissile materials) **Modeling:** - Source term (radionuclide inventory and release) - Near-field (engineered barriers) - Far-field (geosphere transport) - Biosphere (dose to humans and environment) ### 9.2 Dose Calculation **Pathways:** - Groundwater → well → drinking water - Groundwater → irrigation → crops → ingestion - Groundwater → river → fish → ingestion - Direct exposure to contaminated soil **Dose Conversion:** ``` Dose (Sv/y) = Activity (Bq/m³) × Consumption (m³/y) × DCF (Sv/Bq) Where: - DCF = Dose Conversion Factor (isotope-specific) ``` **Regulatory Limits:** - USA: 0.15 mSv/year (10 CFR 61) - Europe: 0.3 mSv/year (typical) - IAEA: 0.3 mSv/year (SSG-23) ### 9.3 Criticality Safety **Conditions for Criticality:** - Sufficient fissile mass - Optimal geometry - Moderator (water) present - Lack of neutron absorbers **Prevention:** - Burnup credit (less reactive) - Boron or gadolinium in baskets - Spacing and geometry control - Limit water intrusion (sealed canisters) **Analysis:** - Keff < 0.95 required (subcritical with margin) - Consider degraded configurations - Conservative assumptions --- ## 10. Implementation Roadmap ### 10.1 Month 7-9: Interim LLW/ILW Storage **Month 7:** - Finalize site selection for near-surface facility - Complete preliminary design - Begin licensing process **Month 8:** - Detailed design and engineering - Procure containers and handling equipment - Environmental assessments **Month 9:** - Site preparation and construction start - Training program development - Procedure writing **Deliverables:** - License application submitted - Construction 30% complete - QA program established ### 10.2 Month 10-12: Dry Cask ISFSI **Month 10:** - Select cask vendor and design - ISFSI site preparation - Procure first casks **Month 11:** - Install storage pads - Commission handling equipment - Dry run training **Month 12:** - Load first casks - Commission monitoring systems - Operational readiness review **Deliverables:** - 10 CFR 72 license approved - First fuel loaded in dry storage - Monitoring program active ### 10.3 Month 13-15: Geological Repository Planning **Month 13:** - Identify 5-10 candidate sites - Desktop geological studies - Stakeholder engagement initiation **Month 14:** - Field investigations (boreholes, geophysics) - Narrow to 2-3 sites - Preliminary design concepts **Month 15:** - Site characterization campaigns - Underground Research Laboratory planning - Environmental impact scoping **Deliverables:** - Site characterization reports - URL conceptual design - Public engagement plan ### 10.4 Month 16-18: Safety Assessment **Month 16:** - Compile all design data - Develop conceptual models - Parameter databases **Month 17:** - Run performance assessment models - Dose calculations for scenarios - Sensitivity and uncertainty analysis **Month 18:** - Safety Assessment Report drafting - Independent peer review - Regulatory interactions **Deliverables:** - Safety Assessment Report complete - Compliance demonstration - Ready for PHASE-3 (Monitoring & Tracking) --- ## Conclusion Phase 2 establishes the physical infrastructure for safe radioactive waste storage and disposal. By completing this phase, organizations will have: 1. **Interim Storage Operational**: Near-surface facilities for LLW/ILW 2. **Dry Cask Storage Active**: ISFSI commissioned for spent fuel 3. **Repository Plan Established**: Site selection process underway for HLW/TRU 4. **Safety Analysis Complete**: Performance assessments demonstrating safety 5. **Regulatory Approvals**: Licenses and permits in hand **Success Metrics:** - Interim storage facility operational with waste emplaced - First dry casks loaded and monitored - Repository candidate sites identified and characterized - Safety assessments showing dose < 0.1 mSv/year - Zero operational incidents or releases **弘益人間** - These engineered and natural barriers protect humanity for millennia, embodying our commitment to future generations. --- **Document Control:** - Version: 1.0.0 - Author: WIA Technical Committee - Review Date: Annual - Previous Phase: PHASE-1.md (Foundation & Classification) - Next Phase: PHASE-3.md (Monitoring & Tracking)