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What is nuclear thermal hydraulics?
, 2020 During the 50’s of the last century, at the start of the exploitation of nuclear fission for the production of electricity, the design and the construction and even the operation of the pioneering reactors occurred without any definition or technology framework for Nuclear Engineering (NE) and, inside NE, Nuclear Thermal-hydraulics (NTH).
D'Auria F., Aksan S., Hassan Y.
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Challenges in Containment Thermal Hydraulics
Nuclear Technology, 2020The containment of a nuclear reactor is a component whose loss in an accident has serious consequences on property, persons, and environment. The Fukushima accident reminded us of this reality.
Studer, E. +15 more
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Thermal-hydraulic Phenomena List
, 2020 A list of 116 Thermal-Hydraulic Phenomena T-HP is derived in the present paper following documents issued during the last three decades by the Committee on the Safety of Nuclear Installations of Nuclear Energy Agency of The Organization for Economic Cooperation and Development (OECD/NEA/CSNI) and by the International Atomic Energy Agency (IAEA).
D'Auria F., Aksan N., Glaeser H.
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Passive systems and nuclear thermal-hydraulics
Nuclear Engineering and Design, 2021Abstract Passive systems are in use within nuclear technology, noticeably those systems, which are capable of transferring thermal power from a heat source to a sink with the use of energy coming from gravity: Natural Circulation inside the vessel for Boiling Water Reactors (BWR) and between vessel and steam generators for Pressurized Water Reactor ...
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Perspectives for Nuclear Thermal Hydraulics
Thermal hydraulics ...
Francesco D'Auria
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FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics
Nuclear Engineering and Design, 2015The purpose of this article is to present briefly the project called Forum & Network of System Thermal-Hydraulics Codes in Nuclear Reactor Thermal-Hydraulics (FONESYS), its participants, the motivation forthe project, its main targets and working modalities.System Thermal-Hydraulics (SYS-TH) codes, also as part of the Best Estimate Plus Uncertainty
Ahn, S.H. +12 more
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Progress in Nuclear Energy, 2009
Abstract The transient thermal-hydraulic problem of MNSR is represented by ten differential equations solved numerically using Runge–Kutta method. Computational results are then compared with experimental measurements. Fuel grids and cooling coil models are incorporated in the model too.
M. Albarhoum, S. Mohammed
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Abstract The transient thermal-hydraulic problem of MNSR is represented by ten differential equations solved numerically using Runge–Kutta method. Computational results are then compared with experimental measurements. Fuel grids and cooling coil models are incorporated in the model too.
M. Albarhoum, S. Mohammed
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2009
After a short review of existing nuclear reactor pressure vessels and core geometry this chapter summarizes the main ideas on how to perform a thermohydraulic analysis of boiling flows in nuclear reactors. Remarkable is that all known threefluid flow patterns and heat transfer mechanisms create the cooling mechanism of the core.
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After a short review of existing nuclear reactor pressure vessels and core geometry this chapter summarizes the main ideas on how to perform a thermohydraulic analysis of boiling flows in nuclear reactors. Remarkable is that all known threefluid flow patterns and heat transfer mechanisms create the cooling mechanism of the core.
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Nuclear Engineering and Design, 2004
Abstract The core thermal–hydraulic design for the HTTR is carried out to evaluate the maximum fuel temperature at normal operation and anticipated operation occurrences. To evaluate coolant flow distribution and maximum fuel temperature, we use the experimental results such as heat transfer coefficient, pressure loss coefficient obtained by mock-up ...
Eiji Takada +3 more
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Abstract The core thermal–hydraulic design for the HTTR is carried out to evaluate the maximum fuel temperature at normal operation and anticipated operation occurrences. To evaluate coolant flow distribution and maximum fuel temperature, we use the experimental results such as heat transfer coefficient, pressure loss coefficient obtained by mock-up ...
Eiji Takada +3 more
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2020
In this chapter, the thermodynamic behavior of thermosyphon and heat pipes is discussed. Following, classical literature thermosyphon and heat pipe thermal and hydraulic models, used in the design of these devices, are presented.
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In this chapter, the thermodynamic behavior of thermosyphon and heat pipes is discussed. Following, classical literature thermosyphon and heat pipe thermal and hydraulic models, used in the design of these devices, are presented.
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