Comparative study of two models simulate a large break LOCA on the pressurized envelope of a typical irradiation test loop using Relap5/SCDAP3.2 system code

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Comparative study of two models simulate a large break LOCA on the pressurized envelope of a typical irradiation test loop using Relap5/SCDAP3.2 system code. / Hadjam, Ahmed; Souidi, Ferhat; Loubar, Ahcene; Wéber, Marcel; Benoit, Philippe (Peer reviewer).

Proceedings of ICAPP 2011. Vol. 1 Paris, France, 2011. p. 1-11.

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Hadjam, A, Souidi, F, Loubar, A, Wéber, M & Benoit, P 2011, Comparative study of two models simulate a large break LOCA on the pressurized envelope of a typical irradiation test loop using Relap5/SCDAP3.2 system code. in Proceedings of ICAPP 2011. vol. 1, Paris, France, pp. 1-11, 2011 - ICAPP - International Congress on Advances in Nuclear Power Plants , Nice, France, 2011-05-02.

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@inproceedings{9c2f10321bc8427c99cca73e4a5f6554,
title = "Comparative study of two models simulate a large break LOCA on the pressurized envelope of a typical irradiation test loop using Relap5/SCDAP3.2 system code",
abstract = "The work presented in this summary is a simulation of a large break loss of coolant accident on the inner pressure tube active section containing the test fuel bundle of the CALLISTO test loop facility (CApabiLity for Light water Irradiation in Steady state and Transient Operation ) using RELAP5/SCDAP3.2 thermal hydraulic system code. The scenario under consideration in this study is the rupture of large size in the inner pressure tube of in pile section of this loop with an initial mass flow rate at the break location of 5 kg/s. Two manners considered to model the accident of LOCA. First, the pressure tubes is simply modelled with a single volume connected to the broken tube with a trip valve, without taking into account the second tube. The second model takes into account the actual geometry of both pressure tubes separated by the space of helium formed in all the pressurized envelope. The latter is modelled in several annulus of different diameters. The break is modelled by a valve between two annulus containing the pressurized water and the Helium. The behaviour of the loop main parameters following this accident in both models is represented graphically and discussed.",
keywords = "LOCA, RELAP5/SCDAP3.2",
author = "Ahmed Hadjam and Ferhat Souidi and Ahcene Loubar and Marcel W{\'e}ber and Philippe Benoit",
note = "Score = 3; 2011 - ICAPP - International Congress on Advances in Nuclear Power Plants ; Conference date: 02-05-2011 Through 06-05-2011",
year = "2011",
month = may,
language = "English",
volume = "1",
pages = "1--11",
booktitle = "Proceedings of ICAPP 2011",

}

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TY - GEN

T1 - Comparative study of two models simulate a large break LOCA on the pressurized envelope of a typical irradiation test loop using Relap5/SCDAP3.2 system code

AU - Hadjam, Ahmed

AU - Souidi, Ferhat

AU - Loubar, Ahcene

AU - Wéber, Marcel

A2 - Benoit, Philippe

N1 - Score = 3

PY - 2011/5

Y1 - 2011/5

N2 - The work presented in this summary is a simulation of a large break loss of coolant accident on the inner pressure tube active section containing the test fuel bundle of the CALLISTO test loop facility (CApabiLity for Light water Irradiation in Steady state and Transient Operation ) using RELAP5/SCDAP3.2 thermal hydraulic system code. The scenario under consideration in this study is the rupture of large size in the inner pressure tube of in pile section of this loop with an initial mass flow rate at the break location of 5 kg/s. Two manners considered to model the accident of LOCA. First, the pressure tubes is simply modelled with a single volume connected to the broken tube with a trip valve, without taking into account the second tube. The second model takes into account the actual geometry of both pressure tubes separated by the space of helium formed in all the pressurized envelope. The latter is modelled in several annulus of different diameters. The break is modelled by a valve between two annulus containing the pressurized water and the Helium. The behaviour of the loop main parameters following this accident in both models is represented graphically and discussed.

AB - The work presented in this summary is a simulation of a large break loss of coolant accident on the inner pressure tube active section containing the test fuel bundle of the CALLISTO test loop facility (CApabiLity for Light water Irradiation in Steady state and Transient Operation ) using RELAP5/SCDAP3.2 thermal hydraulic system code. The scenario under consideration in this study is the rupture of large size in the inner pressure tube of in pile section of this loop with an initial mass flow rate at the break location of 5 kg/s. Two manners considered to model the accident of LOCA. First, the pressure tubes is simply modelled with a single volume connected to the broken tube with a trip valve, without taking into account the second tube. The second model takes into account the actual geometry of both pressure tubes separated by the space of helium formed in all the pressurized envelope. The latter is modelled in several annulus of different diameters. The break is modelled by a valve between two annulus containing the pressurized water and the Helium. The behaviour of the loop main parameters following this accident in both models is represented graphically and discussed.

KW - LOCA

KW - RELAP5/SCDAP3.2

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_116588

UR - http://knowledgecentre.sckcen.be/so2/bibref/8407

M3 - In-proceedings paper

VL - 1

SP - 1

EP - 11

BT - Proceedings of ICAPP 2011

CY - Paris, France

T2 - 2011 - ICAPP - International Congress on Advances in Nuclear Power Plants

Y2 - 2 May 2011 through 6 May 2011

ER -

ID: 172897