CATHARE 2 V2.5_2: A single version for various applications

Geffraye, G.; Antoni, O.; Farvacque, M.; Kadri, D.; Lavialle, G.; Rameau, B.; Ruby, Alain

doi:10.1016/j.nucengdes.2010.09.019

Cited by 100 publications

(39 citation statements)

References 8 publications

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“…CATHARE 2.V2.5 [3] is a multi-purpose multi-reactor concept system code that can describe several kinds of different circuits with various fluids either in single-phase gas or liquid or in two-fluid conditions possibly with noncondensable gases. The code is capable of simulating any kind of reactor concept and any kind of accidental transient.…”

Section: Cathare Codementioning

confidence: 99%

See 1 more Smart Citation

Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/LSTF test 7

Mazgaj

Vacher

Carnevali

2016

EPJ Nuclear Sci. Technol.

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Abstract. Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant design and operation. In the field of Loss Of Coolant Accident, evolutions of the regulations are discussed in various countries taking into account the very unlikely character of a double-ended guillotine break and questioning the necessity to study such an event with Design Basis Conditions assumptions. As a consequence, the consideration of intermediate size piping rupture becomes more and more important. The paper presents the modeling of the Test Facility ROSA-2/LSTF in the calculation code CATHARE 2.V2.5. OECD/NEA ROSA-2 Project Test 7 was conducted with the Large Scale Test Facility on June 14, 2012. The experiment simulated the thermalhydraulic responses during a PWR 13% cold leg Intermediate Break Loss Of Coolant Accident (IBLOCA). The break was simulated by a cold leg upwardly mounted long break nozzle. The facility and the experiment conditions are modeled in CATHARE. The vessel is modeled by using a 3D module. A thermal-hydraulic analysis is conducted and the obtained results are subsequently compared with the experimental results from ROSA-2/ LSTF Test 7. Evaluation of the differences between experimental and calculated results is discussed.

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Section: Cathare Codementioning

confidence: 99%

“…The paper shows the comparison of the experimental results with the calculation results obtained from CATHARE 2.V2.5 [3].…”

Section: Introductionmentioning

confidence: 97%

Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/LSTF test 7

Mazgaj

Vacher

Carnevali

2016

EPJ Nuclear Sci. Technol.

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“…In addition it can be used to quantify conservative analysis margins and for licensing (CEA, 2006). Currently used version CATHARE 2 V2.5 3 is the result of a more than 30 years (the development of CATHARE 1 started in 1979) of joint effort by CEA, EDF (Electricity of France), AREVA NP and IRSN (Radio-protection and Nuclear Safety Institute) (CEA, 2006;Geffraye et al, 2011;Barre and Bernard, 1990).…”

Section: The Cathare Codementioning

confidence: 99%

A review of the current thermal-hydraulic modeling of the Jules Horowitz Reactor: A loss of flow accident analysis

Pegonen

Bourdon

Gonnier

et al. 2014

Nuclear Engineering and Design

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“…This methodology starts with the analysis of the selected scenario by mean a System Thermal-Hydraulic (SYS-TH) code such as RELAP5 [2][3], RELAP5-3D [1], CATHARE2 [4][6], etc. for the analysis of the global behavior of the plant and for the evaluation of the primary side pressure and fluid temperature at the down-comer inlet.…”

Section: Applied Fracture Mechanics 264mentioning

confidence: 99%