The individual channel monitoring (ICM) proposal to improve the safety performance of RBMK

D'Auria, Francesco Saverio; Cherubini, M.; Pierro, F; Giannotti, W.

doi:10.1016/j.nucengdes.2007.03.001

Cited by 8 publications

(2 citation statements)

References 11 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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“…The overpassing of this threshold should cause the PT rupture, pressure increase into the reactor cavity and scram generation signal. Hydraulic blockage (i.e., loss of cooling) of one core channel is discussed in [9]. Investigations allowed the evaluation of the consequences of this event that unavoidably causes the rupture of the pressure tube and the radioactivity release to the NPP confinement system (reactor cavity and accident localization system) and to the environment.…”

Section: Introductionmentioning

confidence: 99%

Thermal-Hydraulic Analysis of Coolant Flow Decrease in Fuel Channels of Smolensk-3 RBMK during GDH Blockage Event

Costa

Cherubini

D'Auria

et al. 2007

Science and Technology of Nuclear Installations

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One of the transients that have received considerable attention in the safety evaluation of RBMK reactors is the partial break of a group distribution header (GDH). The coolant flow rate blockage in one GDH might lead to excessive heat-up of the pressure tubes and can result in multiple fuel channels (FC) ruptures. In this work, the GDH flow blockage transient has been studied considering the Smolensk-3 RBMK NPP (nuclear power plant). In the RBMK, each GDH distributes coolant to 40–43 FC. To investigate the behavior of each FC belonging to the damaged GDH and to have a more realistic trend, one (affected) GDH has been schematized with its forty-two FC, one by one. The calculations were performed using the 0-D NK (neutron kinetic) model of the RELAP5-3.3 stand-alone code. The results show that, during the event, the mass flow rate is disturbed differently according to the power distribution established for each FC in the schematization. The start time of the oscillations in mass flow rate depends strongly on the attributed power to each FC. It was also observed that, during the event, the fuel channels at higher thermal power values tend to undergo first cladding rupture leaving the reactor to scram and safeguarding all the other FCs connected to the affected GDH.

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Applications of SYS TH codes to nuclear reactor design and accident analysis

D'Auria

Galassi

2017

Thermal-Hydraulics of Water Cooled Nuclear Reactors

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The individual channel monitoring (ICM) proposal to improve the safety performance of RBMK

Cited by 8 publications

References 11 publications

Deterministic Safety Technology for RBMK Reactors

Deterministic Safety Technology for RBMK Reactors

Thermal-Hydraulic Analysis of Coolant Flow Decrease in Fuel Channels of Smolensk-3 RBMK during GDH Blockage Event

Applications of SYS TH codes to nuclear reactor design and accident analysis

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