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RISS 인기검색어
- 검색키워드
- 저자 : A. Horváth (검색결과 2 건)
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Behaviour of CFST Stub Columns Subjected to Pure Compression
A. Horváth,D. Kollár,B. Kövesdi 한국강구조학회 2022 International Journal of Steel Structures Vol.22 No.4
Application of concrete-fi lled steel tubes (CFST) is becoming increasingly prominent in the civil engineering practice. However, the interaction of cross-sectional elements in CFST columns raises a number of questions, which have to be investigated in detail to improve design background and analytical resistance formulae. The aim of the current paper is to examine the structural behaviour of innovative concrete-fi lled steel tubes using diff erent structural steel grades (S355, S500 and S960) and concrete classes (C30/37 and C60/75). Combination of normal or high strength steel with normal or high-performance concrete is a novel research topic of composite structures resulting in economic and optimal design for distinct civil engineering applications such as buildings, bridges, towers and masts, etc. An advanced fi nite element model is developed and validated based on previous experimental results found in the international literature in order to investigate the discrepancies in structural behaviour, load-bearing capacity and failure mode of stub columns subjected to pure compression. Validated numerical results are compared to formulae-based resistances and the applicability of standardised design methods are examined. In addition, a novel formula is proposed considering hardening of steel material in accordance with EN 1993-1- 5. The developed formula can be used for the economic design of CFST stub columns, combining normal and high strength materials, where elastic shell buckling cannot occur ( D / t ≤ 90 ε 2 ).
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Assessment of neutron-induced activation of irradiated samples in a research reactor
Harsányi Ildikó,Horváth András,Kis Zoltán,Gméling Katalin,Jozwiak-Niedzwiedzka Daria,Glinicki Michal A.,Szentmiklósi László 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.3
The combination of MCNP6 and the FISPACT codes was used to predict inventories of radioisotopes produced by neutron exposure of a sample in a research reactor. The detailed MCNP6 model of the Budapest Research Reactor and the specific irradiation geometry of the NAA channel was established, while realistic material cards were specified based on concentrations measured by PGAA and NAA, considering the precursor elements of all significant radioisotopes. The energy- and spatial distributions of the neutron field calculated by MCNP6 were transferred to FISPACT, and the resulting activities were validated against those measured using neutron-irradiated small and bulky targets. This approach is general enough to handle different target materials, shapes, and irradiation conditions. A general agreement within 10% has been achieved. Moreover, the method can also be made applicable to predict the activation properties of the near-vessel concrete of existing nuclear installations or assist in the optimal construction of new nuclear power plant units.
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