Results 31 to 40 of about 6,422 (165)
Minimizing the Standard Deviation of the Thermal Load in the Spent Nuclear Fuel Cask Loading Problem
Energies, 2020 The paper assumes that, at the end of the operational period of a Spanish nuclear power plant, an Independent Spent Fuel Storage Installation will be used for long-term storage. Spent fuel assemblies are selected and transferred to casks for dry storage,
Joaquín Bautista-Valhondo +2 more
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A new shielding analysis method for used fuel transport and storage casks
EPJ Web of Conferences, 2017 To provide a cask with the largest possible loading capacity of spent fuel assemblies with the largest practicable burnup and shortest cooling time within all safety requirements, AREVA TN has adapted its design process and developed a more elaborated ...
Léger Vincent, Kitsos Stavros
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Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000
Ядерна фізика та енергетика, 2019 The research presents an analysis of the known results in modeling the maximum design accident (MDA) using the code RELAP5/V3.2 with Westinghouse fuel assemblies’ (WFA) diversification in WWER-1000 reactors.
V. I. Skalozubov +4 more
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Study on fuel management strategy for accident-tolerant fuel on in-pile irradiation test
Frontiers in Energy ResearchWithin the context of the long-term development plan of batch loading of accident-tolerant fuel assemblies, an equivalent physical model of lead test assemblies is established based on the requirements of radiation testing and the applicability of ...
Qingyu Gao +4 more
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ADVANCED HOMOGENIZATION METHODS FOR PRESSURIZED WATER REACTORS
Acta Polytechnica CTU Proceedings, 2018 Macroscopic cross section generation is key part of core calculation. Commonly, the data are prepared independently without a knowledge of fuel loading pattern.
Pavel Suk
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Modification of Neutron Kinetic Code for Plate Type Fuel Nuclear Reactor
Science and Technology of Nuclear Installations, 2013 The research is conducted on the modification of neutron kinetic code for the plate type fuel nuclear reactor. REMARK is a neutron kinetic code that works only for the cylindrical type fuel nuclear reactor.
Salah Ud-Din Khan +2 more
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He jishuBackgroundNatural circulation systems are widely used in the nuclear industry for decay heat removal, post-accident containment cooling, and the cooling of radioactive waste storage facilities.
LI Leilei +5 more
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Void Reactivity Coefficient for Hybrid Reactor Cooled Using Liquid Metal
EnergiesA negative value of the void reactivity coefficient (αV) is one of the most important passive safety properties for the operation of nuclear reactor. Herein, are presented calculated values of the void reactivity coefficient for different geometries of ...
Andrzej Wojciechowski
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EPJ Web of Conferences, 2018 Demand for spent nuclear fuel dry casks as an interim storage solution has increased globally and the IAEA has expressed a need for robust safeguards and verification technologies for ensuring the continuity of knowledge and the integrity of radioactive ...
Harkness Ira +5 more
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Journal of IsotopesHigh energy X-ray non-destructive testing technology can obtain the internal structure information of the inspected object without destroying it. The multi-rod-beam nature of nuclear fuel assemblies can lead to severe scattering ray effects，which can ...
Zhi ZHONG, Gaokui HE, Xiangyang ZHANG
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