IRSN R and D Studies on Fuel Behaviour under LOCA Conditions
Creators
- 1. Giordano, P. DPAM/SEMCA, Bat. 702, Saint-Paul-lez-Durance (France)
Description
The most important safety principle in case of a loss of coolant accident (LOCA) is to preserve the long term coolability of the core. The associated safety requirements are to ensure the resistance of the fuel rods upon quench and post-quench loads and to maintain a coolable geometry in the core. These requirements are formalised in safety criteria, associated with limiting values, mainly expressed through a maximum cladding temperature (PCT) and an equivalent cladding reacted ratio (ECR) with the aim of ensuring a residual ductility of the cladding. In order to prepare acceptance criteria reassessment, IRSN recently conducted an extensive State-of-the-art review relative to fuel behaviour under LOCA conditions. The main pending questions can be summarised under three topics: i) loss of cladding integrity upon quench and post-quench loads, ii) relocation of fuel fragments, iii) flow blockage and core coolability. To address these issues, IRSN is conducting a R and D programme that consists in experiments and code developments. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-192410-0
- Imprint Title
- Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions. Proceedings of a Technical Meeting
- Imprint Pagination
- 398 p.
- Journal Page Range
- p. 179-189
- ISSN
- 1684-2073
- Report number
- IAEA-TECDOC-CD--1709
Conference
- Title
- Technical Meeting on Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions
- Dates
- 18-21 Oct 2011
- Place
- Mito (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44075647
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CLADDING; COMPUTER CODES; DUCTILITY; EXPERIMENTAL DATA; FLOW BLOCKAGE; FUEL RODS; LIMITING VALUES; LOSS OF COOLANT; REACTOR SAFETY; SAFETY STANDARDS; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DATA; DEPOSITION; FUEL ELEMENTS; INFORMATION; MECHANICAL PROPERTIES; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR COMPONENTS; SAFETY; STANDARDS; SURFACE COATING; TENSILE PROPERTIES
Optional Information
- Notes
- 9 figs., 1 tab., 20 refs.