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Annals of Nuclear Energy, ISSN 0306-4549, 12/2019, Volume 134, pp. 101 - 113
Next-generation nuclear reactors are poised to efficiently provide reliable power at enhanced safety levels for many years to come. Among the fundamental... 
Unit cell | Lower plenum | Very-high-temperature reactor (VHTR) | Turbulent mixing | Computational fluid dynamics (CFD) | NUCLEAR SCIENCE & TECHNOLOGY | FLOW | Hydrogen as fuel | Fluid dynamics | Electrolysis | Analysis | Fossil fuels | Nuclear reactors | Energy minerals | Nuclear facilities
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 01/2014, Volume 51, Issue 1, pp. 64 - 76
To estimate the state of reactor pressure vessel of Fukushima Daiichi nuclear power plant, it is important to clarify the breakup and fragmentation of molten... 
lower plenum | molten material jet | severe accident | jet breakup | BWR | fragmentation | two-phase flow | Molten material jet | Severe accident | Two-phase flow | Jet breakup | Lower plenum | Fragmentation | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 11/2019, Volume 133, pp. 236 - 247
One proposed design for a Generation IV reactor is the very-high temperature reactor (VHTR), which employs helium as the primary coolant. Although many... 
Bank of cylinders | Unit cell | Impinging jets | Lower plenum | Very high temperature reactor | Thermal striping | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 02/2016, Volume 53, Issue 2, pp. 147 - 160
To estimate the current status of reactor pressure vessel of Fukushima Daiichi nuclear power plant, it is important to clarify the breakup and the... 
lower plenum | molten material jet | jet breakup | BWR | fragmentation | accident | two-phase flow | NUCLEAR SCIENCE & TECHNOLOGY | Stresses | Computer simulation | Fragments | Nuclear reactor components | Breakup | Boiling water reactors | Shearing | Fragmentation
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 07/2016, Volume 93, pp. 28 - 34
Journal Article
Hedongli Gongcheng/Nuclear Power Engineering, ISSN 0258-0926, 2014, Volume 35, Issue 3, pp. 59 - 63
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 02/2017, Volume 51, Issue 2, pp. 286 - 291
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 08/2014, Volume 51, Issue 7-8, pp. 968 - 976
The jet breakup phenomena of the molten cores during a severe accident are affected by some complicated structures, such as control rod guide tubes, instrument... 
lower plenum | TPFIT | interface tracking method | molten core | severe accident | numerical analysis | jet breakup | BWR | two-phase flow | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Revista Tecnica de la Facultad de Ingenieria Universidad del Zulia, ISSN 0254-0770, 2016, Volume 39, Issue 3, pp. 388 - 396
Journal Article
Journal of Visualization, ISSN 1343-8875, 05/2017, Volume 20, Issue 2, pp. 337 - 348
It is important to clarify the molten material jet breakup process to estimate corium behavior in the lower plenum of a boiling water reactor (BWR). To... 
Isothermal condition | Particle image velocimetry | BWR lower plenum | Severe accident | Jet breakup | FRAGMENTATION BEHAVIOR | COMPUTER SCIENCE, INTERDISCIPLINARY APPLICATIONS | IMAGING SCIENCE & PHOTOGRAPHIC TECHNOLOGY
Journal Article
Journal of Engineering for Gas Turbines and Power, ISSN 0742-4795, 02/2010, Volume 132, Issue 2, p. 22901
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 09/2012, Volume 46, Issue 1, pp. 236 - 239
Journal Article
Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B, ISSN 0387-5016, 2011, Volume 77, Issue 776, pp. 992 - 996
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 12/2010, Volume 44, Issue 12, pp. 1457 - 1463
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 11/2013, Volume 264, pp. 3 - 23
The paper archives the proceedings of an expert panel discussion on the issues and future direction of thermal-hydraulic research and development in nuclear... 
DESIGN | CODE | SAFETY | NUCLEAR SCIENCE & TECHNOLOGY | VHTR | ACCIDENT | WATER-COOLED REACTORS | IN-PHASE STABILITY | LOWER PLENUM | Industrial research | Nuclear energy | Nuclear reactors | Conferences | Computation | Nuclear reactor components | Nuclear engineering | Nuclear power reactors | Nuclear power generation | Research and development
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 11/2015, Volume 52, Issue 11, pp. 1436 - 1447
This paper describes a thermal-hydraulic calculation of an intermediate heat exchanger (IHX) with the computational fluid dynamics (CFD) code CFX. The... 
CFD | lower plenum | IHX | 50 MW SG | heat transfer | Monju | REACTOR | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 10/2016, Volume 307, pp. 354 - 363
A severe accident management strategy known as ‘in-vessel retention (IVR)’ is widely adopted in most of advanced nuclear power plants. The IVR mitigation is... 
SUPPORT | NUCLEAR SCIENCE & TECHNOLOGY | CREEP | REACTOR PRESSURE-VESSEL | COOLABILITY | PWR | MELT RETENTION | SCENARIO | SIMULATION | LOWER PLENUM | Nuclear energy | Nuclear power plants | Accidents
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 03/2012, Volume 46, Issue 3, pp. 299 - 304
Journal Article
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