The cultural connotation of the word "weapon" in Russian and Chinese languages
In: Rossijskij gumanitarnyj žurnal: Liberal arts in Russia, Band 7, Heft 2, S. 141
ISSN: 2312-6442
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In: Rossijskij gumanitarnyj žurnal: Liberal arts in Russia, Band 7, Heft 2, S. 141
ISSN: 2312-6442
In: 9th International Conference on Artificial Intelligence and Applications (AIAPP 2023)
SSRN
In: China population and development studies, Band 2, Heft 3, S. 323-345
ISSN: 2523-8965
In: Science and technology of nuclear installations, Band 2014, S. 1-8
ISSN: 1687-6083
The high temperature gas cooled reactor (HTR) is developing rapidly toward a modular, compact, and integral direction. As the main structure material, graphite plays a very important role in HTR engineering, and the reliability of graphite component has a close relationship with the integrity of reactor core. The graphite components are subjected to high temperature and fast neutron irradiation simultaneously during normal operation of the reactor. With the stress accumulation induced by high temperature and irradiation, the failure risk of graphite components increases constantly. Therefore it is necessary to study and simulate the mechanical behavior of graphite component under in-core working conditions and forecast the internal stress accumulation history and the variation of reliability. The work of this paper focuses on the mechanical analysis of pebble-bed type HTR's graphite brick. The analysis process is comprised of two procedures, stress analysis and reliability analysis. Three different creep models and two different reliability models are reviewed and taken into account in simulation. The stress and failure probability calculation results are obtained and discussed. The results gained with various models are highly consistent, and the discrepancies are acceptable.
In: CSITE-D-22-00209
SSRN
In: International journal of critical infrastructures: IJCIS, Band 19, Heft 4, S. 1
ISSN: 1741-8038
In: International journal of critical infrastructures: IJCIS, Band 19, Heft 3, S. 261
ISSN: 1741-8038
In: International journal of critical infrastructures: IJCIS, Band 20, Heft 4, S. 1
ISSN: 1741-8038
In: Science and technology of nuclear installations, Band 2019, S. 1-15
ISSN: 1687-6083
After the September 11 attack, the resistant capability of containments against aircraft impacts is required to be assessed for newly constructed nuclear power plants (NPPs). In this paper, the crash of a commercial airplane Boeing 767-200ER on the reinforced concrete containment building of an NPP is analyzed using the missile-target interaction method. Two plane models with the same total weight but different fuel distribution are analyzed. The force-time history obtained by FEA (finite element analysis) is compared with the one calculated by the Riera function. In the integral analysis, the mesh sensitivity of the reinforced concrete containment model is studied, and recommendations are provided on the modelling of containment. The impact phenomenon and damage on the containment are investigated through the validated model. The fuel distribution in the aircraft is found to have strong influence on the damage of the containment, which indicates that the load distribution in the transverse direction is critical in the analysis of aircraft impact. The classic load-time function analysis is unable to incorporate this factor and may not be adequate to provide satisfactory results. For this reason, the application of an integral analysis is advantageous in the safety assessment of aircraft impact.
In: International journal of critical infrastructures: IJCIS, Band 15, Heft 1, S. 70
ISSN: 1741-8038
In: Progress in nuclear energy: the international review journal covering all aspects of nuclear energy, Band 152, S. 104364
ISSN: 0149-1970
In: Science and technology of nuclear installations, Band 2022, S. 1-8
ISSN: 1687-6083
The Chinese high-temperature gas-cooled reactor pebble-bed module, HTR-PM, began fuel loading in August 2021. The reactor refuels continuously, while the spent fuel is discharged from the core. The spent fuel conveying and loading system was designed to convey the spent fuel pebbles to the spent fuel building and load them into dry canisters for on-site interim storage. This study describes the operating principles of the main functions and introduces the experiments and commissioning tests of the system. Functional tests were carried out to indicate the items of mechanical and electrical equipment are functioning in accordance with the designed requirements. Experience learned from commissioning activities was also presented as feedback for future operation and design improvement.
In: Environmental science and pollution research: ESPR, Band 29, Heft 16, S. 23963-23974
ISSN: 1614-7499
In: Science and technology of nuclear installations, Band 2017, S. 1-13
ISSN: 1687-6083
The response of nuclear power plants (NPPs) to seismic events is affected by soil-structure interactions (SSI). In the present paper, a finite element (FE) model with transmitting boundaries is used to analyse the SSI effect on the response of NPP buildings subjected to vertically incident seismic excitation. Analysis parameters that affect the accuracy of the calculations, including the dimension of the domain and artificial boundary types, are investigated through a set of models. A numerical SSI analysis for the 10 MW High Temperature Gas Cooled Test Reactor (HTR-10) under seismic excitation was carried out using the developed model. The floor response spectra (FRS) produced by the SSI analysis are compared with a fixed-base model to investigate the SSI effect on the dynamic response of the reactor building. The results show that the FRS at foundation level are reduced and those at higher floor levels are altered significantly when taking SSI into account. The peak frequencies of the FRS are reduced due to the SSI, whereas the acceleration at high floor levels is increased at a certain frequency range. The seismic response of the primary system components, however, is reduced by the analysed SSI for the HTR-10 on the current soil site.
In: Science and technology of nuclear installations, Band 2017, S. 1-14
ISSN: 1687-6083
The graphite is porous medium, and the geometry and size distribution of its structural deficiencies such as microcracks and microvoids at different oxidation degrees have a great influence on the overall performance. In this paper, we adopt the FM-DBEM to study 3D models which contain spheroidal microvoids and circular microcracks. The accuracy of this method is tested by a comparison to the theoretical solution to the problem of 2D microcrack and microvoid interaction problem. Two simulations are conducted: the simulation of graphite model containing a large number of randomly distributed microcracks and microvoids and the simulation of graphite model containing microcracks and growing microvoids. The simulations investigate the effective moduli versus the two microstructures' density and the effect of microvoid's growth on the SIF of microcrack.