Thermal-hydraulic performance of primary system of RBMK in case of accidents

D'Auria, F.; Gabaraev, B. A.; Radkevitch, V.; Moskalev, A.; Ušpuras, E.; Кaliatka, Аlgirdas; Parisi, Carlo; Cherubini, M.; Pierro, F

doi:10.1016/j.nucengdes.2007.03.005

Cited by 22 publications

(3 citation statements)

References 13 publications

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“…The performed thermalhydraulic analyses demonstrate that scram can be actuated early enough to prevent the PT rupture. See also [2][3][4][5][6][7].…”

Section: The Icm Proposalmentioning

confidence: 99%

Deterministic Safety Technology for RBMK Reactors

D'Auria

Soloviev

Mazzini

et al. 2008

Science and Technology of Nuclear Installations

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Recommended by Eugenijus UspurasThe present paper deals with the description of the technical activities conducted within the TACIS Project R2.03/97, 2 EC Contract no. 30303, related to RBMK. The project activities are focused toward the setting-up of a chain of computational tools suitable for the analysis of transients expected in the RBMK nuclear power plant (NPP). The accident leading to the rupture of one pressure channel, with fuel melting or high temperature damage, creep and brittle failure of the pressure tube and of graphite bricks with possibility of rupture propagation, constitutes the reference scenario for the project. However, a series of expected scenarios has been selected to prove the capability of the individual codes or chains of code in simulating the envisaged phenomenology. The paper summarizes the activities performed at NIKIET in Moscow and at University of Pisa (UNIPI) in Pisa. A top-down approach is pursued in structuring the executive summary that includes the following sections: (i) the safety needed for the RBMK NPP, (ii) the roadmap, (iii) the adopted computational tools, (iv) key findings, (v) Emphasis is given to the multiple pressure tube rupture (MPTR) issue and the individual channel monitoring (ICM) proposal.

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“…The performed thermalhydraulic analyses demonstrate that scram can be actuated early enough to prevent the PT rupture. See also [2][3][4][5][6][7].…”

Section: The Icm Proposalmentioning

confidence: 99%

Deterministic Safety Technology for RBMK Reactors

D'Auria

Soloviev

Mazzini

et al. 2008

Science and Technology of Nuclear Installations

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“…Again in Figure 9 it can be seen also the RBMK data. Those calculated values (red and blue stars are obtained by the use of a qualified nodalization developed and tested during an EC funded project [12]. The following consideration come out when calculated data are put inside the NCFM and compared with BWR values.…”

Section: Consideration Of Bwr Datamentioning

confidence: 99%

Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation

Cherubini

Giannotti

Araneo

et al. 2008

Science and Technology of Nuclear Installations

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The aim of this paper is to collect and resume the work done to build and develop, at the University of Pisa, an engineering tool related to the natural circulation. After a brief description of the different loop flow regimes in single phase and two phase, the derivation of a suitable tool to judge the NC performance in a generic system is presented. Finally, an extensive comparison among the NC performance of various nuclear power plants having different design is done to show a practical application of the NC flow map.

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“…All the details from the inception of the problem to the design modification are discussed in the paper. The similar multiple loop boiling water reactor configuration RBMK [47], [48], Fugen ATR [49], [50], are also discussed in the next section.…”

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confidence: 99%