Spent Fuel Behaviour During Interim Storage
Description
Objective: Review of spent fuel data relevant for future storage in Spain Perform destructive and non-destructive examinations on irradiated and non-irradiated fuel rods relevant to Spanish spent fuel management. Research approach: Among the programmes initiated in the last years (finished or about to be finished) one may highlight the following ones: • Isotopic measurements on high burnup fuels: up to 75 GW·d·t(U)-1 PWR and 53 GW·d·t(U)-1 BWR peak values; • Mechanical tests on high burnup PWR (ZIRLO) cladding and BWR (Zry-2) cladding samples; • Mechanical tests on unirradiated ZIRLO rods. Influence of hydrides content; • Modelling of mechanical tests with unirradiated claddings; • Interim storage creep modelling; • Burnup measurement equipment; • Fuel database
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-108215-2
- Imprint Title
- Spent Fuel Performance Assessment and Research. Final Report of a Coordinated Research Project on Spent Fuel Performance Assessment and Research (SPAR-III) 2009#En Dash#2014
- Imprint Pagination
- 222 p.
- Journal Page Range
- p. 195-196
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1771
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47035554
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; CLADDING; CREEP; FUEL MANAGEMENT; HYDRIDES; MECHANICAL TESTS; PWR TYPE REACTORS; RADIOACTIVE WASTE STORAGE; REVIEWS; SPAIN; SPENT FUEL STORAGE; SPENT FUELS
- Descriptors DEC
- DEPOSITION; DEVELOPING COUNTRIES; DOCUMENT TYPES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EUROPE; FUELS; HYDROGEN COMPOUNDS; MANAGEMENT; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; RADIOACTIVE WASTE MANAGEMENT; REACTOR MATERIALS; REACTORS; STORAGE; SURFACE COATING; TESTING; THERMAL REACTORS; WASTE MANAGEMENT; WASTE STORAGE; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Contract/Grant/Project number
- Project 15719