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Peakman A, Owen H, Abram T. Core design and fuel behaviour of a small modular pressurised water reactor using (Th,U)O 2 fuel for commercial marine propulsion. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103966] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Mala P, Pautz A. Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2020.04.022] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Avramova M. Developments in thermal-hydraulic sub-channel modeling for whole core multi-physics simulations. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110387] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Wang J, Wang Q, Ding M. Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107165] [Citation(s) in RCA: 18] [Impact Index Per Article: 4.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: Development and testing based on a computational benchmark. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2019.103138] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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A multi-scale and multi-physics simulation methodology with the state-of-the-art tools for safety analysis in light water reactors applied to a turbine trip scenario (PART I). NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.05.008] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Mitkov S, Spasov I, Kolev NP. Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods. KERNTECHNIK 2018. [DOI: 10.3139/124.110910] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
A hypothetical main steam line break transient in a VVER-1000 core with multiple equipment faults was simulated with the coupled COBAYA4/CTF and COBAYA3/FLICA4 nodal core models. The objective was to test recent versions of the models developed in the EU NURISP and NURESAFE projects and to analyze the thermal-hydraulic conditions in the hot assembly at the pin-cell level. The accident scenario was specified as an aggravated variant of the OECD/NEA VVER-1000 MSLB benchmark with eight peripheral control rod clusters stuck out of the core after scram, all of them in the overcooled sector. Coarse-mesh models and a realistic cross-section library were used to compute the full-core behavior with pre-calculated MSLB boundary conditions and to identify the hot assembly. Then a sub-channel thermal-hydraulic analysis of the hot assembly was performed with the CTF code, using time-dependent assembly boundary conditions from the coarse-mesh vessel and core simulation. The results show that the predicted values of the safety parameters do not exceed the safety limits.
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Affiliation(s)
- S. Mitkov
- Technical University Sofia , Institute for Nuclear Research and Nuclear Energy-BAS, 72 Tsarigradsko chaussee, 1784 Sofia , Bulgaria
| | - I. Spasov
- Technical University Sofia , 8 Kliment Ohridski, 1756 Sofia , Bulgaria
| | - N. P. Kolev
- Technical University Sofia , Institute for Nuclear Research and Nuclear Energy-BAS, 72 Tsarigradsko chaussee, 1784 Sofia , Bulgaria
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Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2017.10.001] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Spasov I, Mitkov S, Kolev N, Sanchez-Cervera S, Garcia-Herranz N, Sabater A, Cuervo D, Jimenez J, Sanchez V, Vyskocil L. Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.03.032] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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