Spent nuclear fuel management after dry storage: fuel integrity and safe handling during fuel encapsulation
Creators
- 1. National Cooperative for the Disposal of Radioactive Waste - Nagra, Wettingen (Switzerland)
- 2. European Commission, Joint Research Centre (JRC), Directorate for Nuclear Safety and Security, Karlsruhe (Germany)
- 3. Wissenschaftlich-Technische Ingenieurberatung GmbH (WTI), Jülich (Germany)
Description
In Switzerland, the spent nuclear fuel assemblies arising from the operation of the five NPPs are currently stored in pools at the NPP sites and, after a cooling period, are transferred to transport/storage casks which are then transported and stored in centralized dry interim storage facilities. The National Cooperative for the Disposal of Radioactive Waste (Nagra) has proposed deep geological disposal as the solution for the management of all radioactive waste. Pre-disposal activities, in particular for the spent fuel encapsulation facility and related unloading/loading and handling operations from the transport/storage casks into the final disposal canisters, are safety-relevant operations. Nagra therefore initiated several studies and RD&D activities aimed at assessing spent fuel mechanical performance, but also at developing concepts for handling of consequence scenarios. Concerning the RD&D program, the main objective of the investigations is to assess the response of spent fuel rods to mechanical stresses corresponding to normal conditions and accident scenarios by means of experiments on PWR spent fuel rod segments. The experimental campaign is conducted at JRC Karlsruhe, with the focus on the effect of hydrogen load, hydride distribution and pellet/cladding interaction on the cladding integrity. Other studies are currently under development to investigate the deterioration of the cladding properties resulting from Delayed Hydride Cracking (with Paul Scherrer Institute), as well as the deterioration of the FA structural material for long-term dry storage conditions (with Framatome GmbH). Furthermore, a conceptual study is under development to establish specific technical requirements for the encapsulation facility, focusing on fuel handling, retrieval and packaging operations. The main scope is to ensure the safe management of any damaged and degraded fuel and to implement measures for the mitigation of accident scenarios. Key aspects and main achievements of these ongoing programs are presented here. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108620-4
- Imprint Title
- Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, Enabling the Future. Proceedings of an International Conference
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 9 p.
- ISSN
- 0074-1884
Conference
- Title
- Learning from the past, enabling the future
- Acronym
- International conference on management of spent fuel from nuclear power reactors
- Dates
- 24-28 Jun 2019
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51073780
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; COOLING TIME; DAMAGE; DRY STORAGE; ENCAPSULATION; FUEL ASSEMBLIES; FUEL INTEGRITY; FUEL MANAGEMENT; FUEL RODS; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; PACKAGING RULES; PWR TYPE REACTORS; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; RESEARCH PROGRAMS; SAFETY; SPENT FUEL CASKS; SPENT FUELS; STORAGE FACILITIES; STRESSES; SWITZERLAND; UNDERGROUND DISPOSAL; WASTE TRANSPORTATION
- Descriptors DEC
- CASKS; CONTAINERS; DEPOSITION; DEVELOPED COUNTRIES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EUROPE; FUEL ELEMENTS; FUELS; INDUSTRY; LAWS; MANAGEMENT; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; POWER PLANTS; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; REGULATIONS; STORAGE; SURFACE COATING; THERMAL POWER PLANTS; THERMAL REACTORS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE STORAGE; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- 24 refs., 5 figs.
- Secondary number(s)
- IAEA-CN--272/50