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Abstract
In this work, we present the first dynamic calculations performed with the Monte Carlo neutron transport code TRIPOLI-4R with thermal-hydraulics feedback. For this purpose, the Monte Carlo code was extended for multi-physics capabilities and coupled to the thermal-hydraulics subchannel code SUBCHANFLOW. As a test case for the verification of transient simulation capabilities, a 3x3-assembly mini-core benchmark based on the TMI-1 reactor is considered with a pin-by-pin description. Two reactivity excursion scenarios initiated by control-rod movement are simulated starting from a critical state and compared to analogous simulations performed using the Serpent 2 Monte-Carlo code. The time evolution of the neutron power, fuel temperature, coolant temperature and coolant density are analysed to assess the multi-physics capabilities of TRIPOLI-4. The stabilizing e_ects of thermal-hydraulics on the neutron power appear to be well taken into account. The computational requirements for massively parallel calculations are also discussed.
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An overview of TACIS and PHARE nuclear safety projects related to thermalhydraulics. PROGRESS IN NUCLEAR ENERGY 2012. [DOI: 10.1016/j.pnucene.2012.02.009] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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D’Auria F, Gabaraev B, Radkevitch V, Moskalev A, Uspuras E, Kaliatka A, Parisi C, Cherubini M, Pierro F. Thermal-hydraulic performance of primary system of RBMK in case of accidents. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.03.005] [Citation(s) in RCA: 14] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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D’Auria F, Gabaraev B, Soloviev S, Novoselsky O, Moskalev A, Uspuras E, Galassi G, Parisi C, Petrov A, Radkevich V, Parafilo L, Kryuchkov D. Deterministic accident analysis for RBMK. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.03.006] [Citation(s) in RCA: 12] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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D’Auria F, Gabaraev B, Novoselsky O, Radkevich V, Filinov V, Mazzini D, Moretti F, Pierro F, Vigni A, Parafilo L, Kryuchkov D. The multiple pressure tube rupture (MPTR) issue in RBMK safety technology. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.03.002] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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D’Auria F, Novoselsky O, Safonov V, Uspuras E, Galassi G, Cherubini M, Giannotti W. Thermal–hydraulic performance of confinement system of RBMK in case of accidents. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.03.004] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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D’Auria F, Cherubini M, Pierro F, Giannotti W. The individual channel monitoring (ICM) proposal to improve the safety performance of RBMK. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.03.001] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Deterministic Safety Technology for RBMK Reactors. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2008. [DOI: 10.1155/2008/781824] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
Abstract
The 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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