Published May 2020 | Version v1
Book

Spent nuclear fuel management after dry storage: fuel integrity and safe handling during fuel encapsulation

  • 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)

Part of:
Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, Enabling the Future. Proceedings of an International Conference

Additional details

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)

Optional Information

Notes
24 refs., 5 figs.
Secondary number(s)
IAEA-CN--272/50