Outcome of work at Centro Atómico Constituyentes (CAC), Argentina [CRP contributors scope and outcome]
Creators
Description
The objective of this contribution is the analysis of the potential ageing degradation mechanisms for very long term (more than 100 years) of Atucha 1 spent fuel, in relation with its transport from storage pool to a dry storage facility. Atucha 1 is a pressurized heavy water reactor (PHWR) using slightly enriched uranium oxide fuel with Zircaloy-4 cladding. In addition, other important aspects related to the performance of the facility in this time frame have been addressed within this CRP, as ageing degradation of concrete structures. The activities in this contribution carried out during the development of the CRP include a bibliographic state-of-the-art review on SNF Zircaloy-4 cladding ageing degradation mechanisms, as well as experimental work aimed at filling the identified gaps.
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-103319-2
- Imprint Title
- Demonstrating Performance of Spent Fuel and Related Storage System Components during Very Long Term Storage. Final Report of a Coordinated Research Project
- Imprint Pagination
- 212 p.
- Journal Page Range
- p. 69-71
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1878
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50071298
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- AGING; ARGENTINA; ATUCHA-1 REACTOR; CONCRETES; DECOMPOSITION; DRY STORAGE; HEAVY WATER COOLED REACTORS; SLIGHTLY ENRICHED URANIUM; SPENT FUELS; STORAGE FACILITIES; URANIUM OXIDES; ZIRCALOY 4
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALLOYS; ALLOY-ZR98SN-4; BUILDING MATERIALS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEVELOPING COUNTRIES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRON ADDITIONS; IRON ALLOYS; ISOTOPE ENRICHED MATERIALS; LATIN AMERICA; MATERIALS; METALS; NATURAL URANIUM REACTORS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; SOUTH AMERICA; STORAGE; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM; URANIUM COMPOUNDS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Fig. Imprint:CD-ROM attached to the printed IAEA-TECDOC-1878 containing Annexes I-XIV as supplementary material