Published September 2007 | Version v1
Journal article

Coolability of blocked regions in a rod bundle after ballooning under LOCA conditions

  • 1. Institut de Radioprotection et de Surete Nucleaire (IRSN), DPAM, BP3 13115 St. Paul-Lez-Durance (France)

Description

IRSN has carried out a state-of-the-art review of the main experimental programmes related to fuel behaviour under loss-of-coolant-accident (LOCA) conditions conducted from the 1970s until now, that has been split in three parts. The second part is devoted to the question of the coolability of blocked regions in a rod bundle after ballooning in a LOCA. The main findings from this part are presented here. The experimental characteristics and main results of the FEBA, SEFLEX, THETIS, ACHILLES, CEGB and FLECHT-SEASET programmes, as well as several analytical developments performed in association with these experimental programmes, were examined in detail in this review. The comparison and combination of conclusions drawn from these results and studies were used to improve our understanding of the physical phenomena governing the behaviour of a partially blocked rod array during a LOCA reflood scenario. It has also been possible to determine the limits of blockage coolability under the most severe geometric (blockage ratio and length) and thermohydraulic conditions. Thus, even a severe blockage ratio (90%) of a moderate length (<10 cm) does not cause any particular problems in terms of coolability during two-phase reflood. However, a severe blockage with considerable axial extension (>15 cm) and a high blockage ratio (>80%) can lead - under low reflood conditions - to a significant increase in blockage surface temperatures, hindering the final coolability of this blockage. It is important to underline that these results were obtained in out-of-pile experiments performed with electrically heated fuel rod simulators with a large gap between simulator and cladding bulge, thus not allowing to simulate the possible fuel accumulation occurring in cladding balloons (fuel relocation), as was observed during all in-pile tests with irradiated fuel rods. The impact of fuel relocation upon blockage coolability therefore remains to be investigated

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2007.02.022;
PII
S0029-5493(07)00203-8;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
237
Journal Issue
15-17
Journal Page Range
p. 1872-1886
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
11. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-11
Dates
2-6 Oct 2005
Place
Avignon (France)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
38090115
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BALLOONING INSTABILITY; CLADDING; FUEL ELEMENT CLUSTERS; FUEL RODS; LENGTH; LOSS OF COOLANT; SIMULATORS; SPENT FUELS
Descriptors DEC
ACCIDENTS; ANALOG SYSTEMS; DEPOSITION; DIMENSIONS; ENERGY SOURCES; FUEL ASSEMBLIES; FUEL ELEMENTS; FUELS; FUNCTIONAL MODELS; INSTABILITY; MATERIALS; NUCLEAR FUELS; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; SURFACE COATING

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.