Research Activities Related to Fuel Dry Storage: France
Creators
Description
Activities for understanding fuel behaviour in various conditions are performed in France by IRSN, CEA, and for the impact conditions by Orano TN. Concerning the situation of spent nuclear fuel in dry storage and subsequent transportation, only a few recent results have been released since SPAR-III. CEA previously presented the results of their activities for understanding fuel rod cladding behaviour, such as creep, oxidation, hydride precipitation, hydrogen effects, delayed hydride cracking, and embrittlement. In addition, some other studies covered the behaviour of fuel pellets inside the rods (pellet swelling, fission gas release). A new model on radial hydride precipitation in Zircaloy-4 claddings under decay stress and temperature transient was presented at the 2015 IAEA International Conference "Management of Spent Fuel from Nuclear Power Reactors". In summary, radial hydride precipitation is considered as an important issue for Zircaloy-4 claddings in spent fuel transportation and storage.
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-128221-7
- Imprint Title
- Spent Fuel Performance Assessment and Research. Final Report of a Coordinated Research Project (SPAR-IV)
- Imprint Pagination
- 160 p.
- Journal Page Range
- p. 41
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1975
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52119373
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CEA; CLADDING; CREEP; DRY STORAGE; EMBRITTLEMENT; FISSION PRODUCT RELEASE; FUEL PELLETS; FUEL RODS; HYDRIDES; HYDROGEN; NUCLEAR DECAY; NUCLEAR POWER PLANTS; OXIDATION; PRECIPITATION; RODS; SPENT FUELS; SWELLING; TRANSIENTS; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-4; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DECAY; DEFORMATION; DEPOSITION; ELEMENTS; ENERGY SOURCES; FRENCH ORGANIZATIONS; FUEL ELEMENTS; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; NONMETALS; NUCLEAR FACILITIES; NUCLEAR FUELS; PELLETS; POWER PLANTS; REACTOR COMPONENTS; REACTOR MATERIALS; SEPARATION PROCESSES; STORAGE; SURFACE COATING; THERMAL POWER PLANTS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS