Results 251 to 260 of about 1,398,280 (304)

The future of nuclear thermal-hydraulics

Nuclear Engineering and Design, 2019
Abstract An attempt is made to identify perspectives in nuclear thermal-hydraulics based on devoted papers published during the last seven years. An understandable target is fixed which also appears consistent with the framework of this Special Issue (SI).
D’Auria F., Aksan N., Hassan Y.
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Perspectives in nuclear thermal hydraulics

The chapter deals with two topics: 1) evaluation of nuclear thermal hydraulics (NTH) as it derives from the proposed scope; 2) perspectives/proposals for development in the area. Referring to the former topic: NTH implies a universe of knowledge, which, among the other things, is not easy to summarize and is correctly described from different ...
D’Auria Francesco, Hassan Y., Kim K-D., Bestion D.   +3 more
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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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Containment thermal hydraulics

The investigation of transient thermal hydraulic performance of nuclear reactor containments constitutes the topic of the present chapter. Standard nuclear thermal hydraulic equations and models, i.e. adopted for accident analysis in primary circuit and discussed in different chapters of the book, are applicable here.
Rohatgi U. S., D'Auria Francesco
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Challenges in Containment Thermal Hydraulics

Nuclear Technology, 2020
The 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., Abdo, D., Benteboula, S., Bernard-Michel, G., Cariteau, B., Coulon, N., Dabbene, F., Debesse, Ph., Koudriakov, S., Ledier, C., Magnaud, J.-P., Norvez, O., Widloecher, J.-L., Beccantini, A., Gounand, S., Brinster, J.   +15 more
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Passive systems and nuclear thermal-hydraulics

Nuclear Engineering and Design, 2021
Abstract 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, 2015
The 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., Aksan, N.,, Bestion, D., Chung, B.D., D'Auria, F., Emonot, P., Gandrille, J.L., Hänninen, Markku, Horvatovic, I., Kim, K.D., Kovtonyuk, A., Petruzzi, A.   +12 more
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A thermal-hydraulic code (THYD) for the miniature neutron source reactor thermal-hydraulic transients

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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Core thermal–hydraulic design

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, Shigeaki Nakagawa, Nozomu Fujimoto, Daisuke Tochio   +3 more
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