An International Spent Nuclear Fuel Storage Facility Exploring a Russian Site as a Prototype: Proceedings of an International Workshop (2005) / Chapter Skim
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The High Level Waste Disposal Technology Development Program in Korea
The High Level Waste Disposal Technology Development Program in Korea
Pages 50-58
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From page 50... ...
Many different alternatives concerning the emplacement patterns of the container, waste packaging methods, as well as the distance between deposition holes and tunnels were proposed, as seen in most countries that have established their own disposal concepts for high-level waste. From the comparison of the proposed alternatives1 the VSA concept, or vertical emplacement of separate packaging containers in separate areas, was suggested as the reference disposal concept and horizontal emplacement of containers in separate areas (the HAS concept)
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From page 51... ...
: 385 watt/assembly for PWR, 2.28 watt/bundle for CANDU · The container filling material for void space within the container: carbon steel · Emplacement sequence: CANDU spent fuel first, followed by PWR spent fuel · Backfill design: vertical boreholes with bentonite buffer · Repository layout: single-level repository · Throughput: dictated by a 50-year operational life of repository · Thermal constraints: surface temperature of disposal container limited to 100°C · Waste package configuration: 4 PWR assemblies and 297 CANDU bundles · Borehole spacing: 3 m (CANDU)
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From page 52... ...
Underground Facilities The conceptual repository layout builds on the information and key constraints that define the emplacement tunnel dimensions and borehole separation distances, borehole layouts, and waste-receipt schedules. Figure 1 shows the isometric view of the various underground openings, including the disposal area, the service shaft complex, and the ventilation exhaust shaft complex.
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From page 53... ...
53 repository. geological conceptual preliminary the of view Isometric 1 FIGURE
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From page 54... ...
The engineered barrier system is composed of the waste types, the surrounding waste package, other engineered items in the underground facility, and buffer and backfill material. Design features of the engineered barrier system are the waste type, the waste canister package, and a bentonite buffer.
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From page 55... ...
As shown in Figure 3, the outer shell contains fuel storage baskets (4 square tubes for spent PWR fuel and 33 circular tubes for spent CANDU fuel) , and the void space between the fuel storage basket and the outer shell is filled with carbon steel called the cast insert.
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From page 56... ...
: Carbon steel Cast Insert (Fuel region) : Carbon steel Capacity: 4 PWR spent fuel assemblies Capacity: 297 bundles (33 tubes x 9 stacks)
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From page 57... ...
The disposal concept being considered at present includes borehole emplacement in the floors and subsequent backfilling of the emplacement tunnels. The base-case repository may include backfilling, particularly of the emplacement tunnels, immediately after waste emplacement or 50- to 100-year monitored retrieval operations.
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From page 58... ...
Kang. Structural analysis for the determination of design variables of spent nuclear fuel disposal canister.
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