Published June 2013 | Version v1
Report

IRSN R and D Studies on Fuel Behaviour under LOCA Conditions

  • 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)

Part of:
Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions. Proceedings of a Technical Meeting

Additional details

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.