Results 1 to 10 of about 10,412 (178)
Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика, 2018 Tgratinghis paper presents the results of experimental investigations of the influence of mixing spacer gratings with different types of deflectors on the coolant flow in the TVSKvadrat fuel assembly of the PWR-type reactor. Experimental model of the TVS-
S. M. Dmitriev +4 more
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Analytical dependence of burnup on enrichment of prospective fuel and parameters of reactors fuel campaign [PDF]
Nuclear Energy and Technology, 2023 The paper is devoted to the definition of an analytical expression for estimating the burnup depth of nuclear fuel depending on its enrichment level, the periodicity of refueling, thermal stressthermal stress and the duration of the time period between ...
Evgeny V. Semenov +1 more
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Study of natural uranium fuel for a new reactor design TEPLATOR [PDF]
EPJ Web of Conferences, 2021 The TEPLATOR is a new type of nuclear reactor which the main purpose is producing heat for district heating. It is designed as a special thermal reactor with 55 fuel channels for fuel assemblies, which is moderated and cooled by heavy water and operated ...
Peltan Tomas, Vilimova Eva, Skoda Radek
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SERPENT/SUBCHANFLOW COUPLED BURNUP CALCULATIONS FOR VVER FUEL ASSEMBLIES [PDF]
EPJ Web of Conferences, 2021 The continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ commercial goals represent a push for the development of highly accurate methodologies in reactor physics.
Ferraro Diego +6 more
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Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core [PDF]
Nuclear Energy and Technology, 2022 Advanced pressurized water reactors are the main part of a new generation of nuclear power plant projects under development that provide cost-effective power production for various needs (Yemelyanov et al. 1982, Klimov 2002, Boyko et al.
Vyacheslav S. Kuzevanov +1 more
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MELCOR steady state calculation of the generic PWR of 40MWth
Brazilian Journal of Radiation Sciences, 2021 After the two most significant nuclear accidents in history – the Chernobyl Reactor Four explosion in Ukraine (1986) and the Fukushima Daiichi accident in Japan (2011) –, the Final Safety Analysis Report (FSAR) included a new chapter (19) dedicated to ...
Maritza Rodríguez Gual +2 more
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Verification of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessel
Mechanical Engineering Journal, 2023 A probabilistic fracture mechanics (PFM) analysis code, PASCAL, has been developed by Japan Atomic Energy Agency for failure probability and failure frequency evaluation of reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and
Kai LU +10 more
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Local and high distance neutron and gamma measurements of fuel rods oscillation experiments [PDF]
EPJ Web of Conferences, 2021 We report in the present article on the successful observation using noise analysis of the lateral oscillation of one fuel rod by ±2.5 mm around nominal at 0.1 Hz frequency, using an mm3 miniature neutron scintillator at the rod level, and a BGO gamma ...
Lamirand Vincent +6 more
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Integral PWR-Type Small Modular Reactor Developmental Status, Design Characteristics and Passive Features: A Review [PDF]
Energies, 2020 In recent years, the trend in small modular reactor (SMR) technology development has been towards the water-cooled integral pressurized water reactor (iPWR) type. The innovative and unique characteristics of iPWR-type SMRs provide an enhanced safety margin, and thus offer the potential to expand the use of safe, clean, and reliable nuclear energy to a ...
Chireuding Zeliang +4 more
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Nuclear Engineering and Technology, 2023 A protective oxide layer forms on the material surfaces of a Nuclear Power Plant during operation due to high temperature. These oxides can host radionuclides, the activated corrosion products of fission products, resulting in decommissioning workers ...
Ayantika Banerjee +4 more
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