Published January 18, 2011 | Version v1
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Validation of an improved reflooding model in ICARE-CATHARE code: QUENCH 11 test calculation

  • 1. Institut de Radioprotection et Surete Nucleaire - IRSN, Fontenay-aux-Roses (France)

Description

In case of the loss of coolant accident (LOCA) the prime accident management procedure consists in injecting water in the reactor core, by means of various safety injection devices. Nevertheless, the success of a core reflood is not guaranteed because of possible negative effects. The success of a core reflood depends mainly on the core state (geometry and temperature), the primary pressure and the injection rate. The description of the reflooding phase, for any core configuration, is one of the objectives of ICARE/CATHARE V2 code. A new reflooding model has been implemented in the ICARE-CATHARE V2 code, improving significantly the tracking of quench front and the accuracy of heat transfer calculation in the transition boiling zone. This new model has been qualified on QUENCH 11 test showing that the model is also valid for very high temperature of claddings and when rods are slightly damaged. The new model changes the thermalhydraulic behaviour and results in a better prediction of hydrogen production. It confirms that the understanding of thermal-hydraulic phenomena is a key point in the safety management, as important as the kinetic of oxidation. At high temperature, kinetic rate is so fast that the reaction is limited by steam availability. The impact of the injection on the hydrogen production has been studied. The conclusion is that injecting water during a severe accident is not an obvious procedure. If the flow rate is too low, the hydrogen production may increase significantly

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Part of:
In-Vessel Coolability. Workshop Proceedings, in collaboration with EC-SARNET

Additional details

Publishing Information

Imprint Title
In-Vessel Coolability. Workshop Proceedings, in collaboration with EC-SARNET
Imprint Pagination
572 p.
Journal Page Range
p. 393-418
Report number
NEA-CSNI-R--2010-11

Conference

Title
Workshop on In-Vessel Coolability
Dates
12-14 Oct 2009
Place
Issy-les-Moulineaux (France)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
48026398
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; C CODES; COMPUTERIZED SIMULATION; COOLING; HEAT TRANSFER; HYDROGEN; I CODES; LOSS OF COOLANT; MELTDOWN; PWR TYPE REACTORS; VALIDATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 refs.