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Elevated CO₂ Increases the Canopy Temperature of Mature Quercus robur (Pedunculate Oak). [PDF]

Glob Chang Biol
Hagan Brown W, Gloor E, Fyfe R, MacKenzie AR, Harper NJ, Ganderton P, Hart K, Curioni G, Quick S, Davidson SJ, Yetton E, Diehl JL, Fauset S.   +12 more
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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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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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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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Core thermal hydraulic

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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Nuclear thermal-hydraulics: What is it?

Nuclear Engineering and Design, 2019
Abstract B. R. Sehgal, G. Yadigaroglu and G. Hewitt spent their scientific lives in nuclear thermal-hydraulics and closely connected areas and sturdily contributed to the development. What is nuclear thermal-hydraulics nowadays? It has been defined as a universe of matters, knowledge and competences; any scientist attempting to answer the question ...
D'Auria F., N. Aksan, Y. Hassan
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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., Austregesilo, H., Bestion, D., Chung, B. D., D'AURIA, FRANCESCO SAVERIO, Emonot, P., Gandrille, J. L., Hanninen, M., Horvatović, I., Kim, K. D., Kovtonyuk, A., Petruzzi, A.   +12 more
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Core Thermal Hydraulics Design

2011
In the previous chapter we explored the methodology for determining the temperature field for a single fuel pin. Since a typical fast reactor core comprises several thousand fuel pins clustered in groups of several hundred pins per assembly, a complete thermal-hydraulic analysis requires knowledge of coolant distributions and pressure losses throughout
Alan Waltar, Donald Todd
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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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