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An International Spent Nuclear Fuel Storage Facility -- Exploring a Russian Site as a Prototype: Proceedings of an International Workshop (2005)
Development, Security, and Cooperation (DSC)

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. "The High Level Waste Disposal Technology Development Program in Korea." An International Spent Nuclear Fuel Storage Facility -- Exploring a Russian Site as a Prototype: Proceedings of an International Workshop. Washington, DC: The National Academies Press, 2005.

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An International Spent Nuclear Fuel Storage Facility: Exploring a Russian Site as a Prototype - Proceedings of an International Workshop

ceptual design study includes the layout of the underground facilities, the engineered barrier system, and the dimensions of the major repository system components needed to support the reference repository system design. This study is not site specific, because there are no site characterization data requiring repository performance to a specific location. Many design parameters and criteria are necessarily general or assumed.

DESIGN BASES

These design bases provide the information that identifies the specific functions to be performed by the repository system, as well as the specific values or ranges of values chosen as controlling parameters to bound the design. As a general guideline for this study2 the conceptual repository will be located in granitic rock, the major rock type in Korea, at a depth nominally of 500 m between two large fault zones that extend from this depth to the surface. The rock quality varies from highly weathered surface deposits to competent rock at the repository horizon. For this conceptual design the distance between faults should be about 7 to 10 km. Therefore, the repository layout must be capable of fitting within these major structural features. The most stringent requirement for the base-case underground facility is that the temperature of the bentonite buffer material remains below 100°C throughout the lifetime of the repository.

The development of the underground repository system conceptual design requires specifications of (1) design constraints and criteria, (2) disposal canister design, and (3) waste form and throughput. Key design constraints are summarized in Box 1.

BOX 1
Specifications for the Conceptual Design of an Underground Repository

  • Total spent fuel inventory to be packaged for disposal: 36,000 tHM[2]

  • Decay heat (40-year cooling): 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) and 6 m (PWR)

  • Drift spacing: 40 m

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Front Matter (R1-R12)
Opening Remarks (1-2)
Handling Spent Nuclear Fuel—International Experience -- IAEA Activities in Nuclear Spent Fuel Management (3-11)
Analysis of U.S. Experience with Spent Fuel (12-19)
Problems of Spent Nuclear Fuel Management and Storage Site Selection (20-29)
Feasibility of Transmutation of Radioactive Elements (30-49)
The High Level Waste Disposal Technology Development Program in Korea (50-58)
The Use of Sodium-Cooled Fast Reactors for Effectively Reprocessing Plutonium and Minor Actinides (59-72)
Site Selection for Spent Fuel Storage and Disposal of High Level Waste -- Site Selection for Spent Fuel Storage and Disposal of High Level Waste: Experience of European Countries (73-88)
The Private Fuel Limited Liability Company National Spent Fuel Site (89-95)
Experience of Japan (96-108)
The Current Status of Spent Nuclear Fuel in Korea (109-117)
Safe Transport of Spent Nuclear Fuel and High Level Waste: International Experience (118-127)
Ensuring Nuclear and Radiation Safety During the Transport of Radioactive Materials in Russia (128-142)
Problems in Establishing an International Repository for Spent Nuclear Fuel in Russia -- Creating an Infrastructure for Managing of Spent Nuclear Fuel (143-151)
Current Status of Government Regulation of Activities Associated with the Import of Spent Nuclear Fuel into the Russian Federation Return to the Russian Federation of Irradiated Fuel Assemblies from the Institute of Nuclear Physics of the Republic of Uzbekistan (152-158)
Return to the Russian Federation of Irradiated Fuel Assemblies from the Institute of Nuclear Physics of the Republic of Uzbekistan (159-162)
Investment and International Aspects of the Problem of Spent Nuclear Fuel Management (163-165)
Creation of an Underground Repository for Spent Nuclear Fuel near the City of Zheleznogorsk (Eastern Siberia) (166-176)
Conditions for the Creation of an International Spent Nuclear Fuel Repository near the Priargunsk Mining-Chemical Production Association (City of Krasnokamensk, Chita Oblast) (177-186)
Utilization of High-Level Waste -- Types of High-Level Radioactive Wastes Formed as a Result of Dry Methods of Spent Fuel Regeneration and Technologies for their Management (187-198)
Chemical Treatment of High Level Waste for Utilization (199-207)
Immobilization of High Level Waste: Analysis of Appropriate Synthetic Waste Forms (208-224)
The Management of High-Level Radioactive Wastes from the Mayak Production Association and Plans for the Creation of an Underground Laboratory (225-239)
Creation of Underground Laboratories at the Mining-Chemical Complex and at Mayak to Study the Suitability of Sites for Underground Isolation of Radioactive Wastes (240-247)
Concluding Observations--Milton Levenson (248-250)
Appendix A: Workshop Agenda (251-256)
Appendix B: Environmental Effects of Radiation in the Russian Federation (257-259)
Appendix C: Geochemistry of Actinides During the Long-Term Storage and Disposal of Spent Nuclear Fuel (260-290)