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Rintala A, Valtavirta V, Leppänen J. Microscopic cross section calculation methodology in the Serpent 2 Monte Carlo code. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108603] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Wibisono AF, Shwageraus E. CORE DESIGN STUDY FOR A SMALL MODULAR BOILING WATER REACTOR. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124719001] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
The hybrid Small Modular Boiling Water Reactor (SMBWR) is a new conceptual design of BWR-type SMR. The main features of SMBWR include a natural circulation loop in its coolant recirculation system and external superheaters system integrated into the steam cycle. A full core analysis of SMBWR is performed with the nodal diffusion code PANTHER using homogenised constant libraries generated by WIMS. The study compared a number of core geometry configurations and fuel management schemes to suppress excess reactivity throughout fuel depletion. Three options for SMBWR core aspect ratio using the same power density are investigated with the aim to assess the effect on the neutronic and thermal-hydraulic performance of the SMBWR. It is found that the thin and tall core configuration (192 fuel assemblies and 3.60 m) showed the least favourable performance out of the three options as it has the largest core pressure drop and thus requires taller chimney to develop natural circulation.
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Kliem S, Grahn A, Bilodid Y, Höhne T. A realistic approach for the assessment of the consequences of heterogeneous boron dilution events in pressurized water reactors. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.04.038] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Applying the Serpent-DYN3D code sequence for the decay heat analysis of metallic fuel sodium fast reactor. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.11.020] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Bilodid Y, Fridman E, Kotlyar D, Shwageraus E. Explicit decay heat calculation in the nodal diffusion code DYN3D. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.07.045] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Abstract
AbstractThe reactor safety research of the Helmholtz Association is an integral part of the national provident research. It focuses on the safety of nuclear power plants in Germany and abroad as well as on safety aspects of internationally developed innovative reactor concepts. The research in the three involved Helmholtz centers Forschungszentrum Jülich, Helmholtz-Zentrum Dresden-Rossendorf and Karlsruhe Institute of Technology covers important areas of design basis and beyond design basis accidents. A unique combination of code and model development supported by own large-scale experiments ensures the active preservation of the reactor safety competences. The research that is embedded in a strong international co-operation will be continued after the completion of the national phase-out from the use of nuclear energy for electricity production in 2022.
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Affiliation(s)
- S. Kliem
- 1Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstraße 400, D-01328 Dresden
| | - W. Tromm
- 2Karlsruhe Institute of Technology, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen, E-mail:
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Rohde U, Seidl M, Kliem S, Bilodid Y. Neutron noise observations in German KWU built PWRs and analyses with the reactor dynamics code DYN3D. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.10.033] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Huang K, Wu H, Li Y, Cao L. Depletion system compression method with treatment of decay heat. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2017.03.022] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Simulation of an MSLB scenario using the 3D neutron kinetic core model DYN3D coupled with the CFD software Trio_U. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.02.002] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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