Guillaume Gesmier , Shixian Wang , Shuichiro Miwa , Koji Okamoto
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引用次数: 0
Abstract
This study investigates critical heat flux (CHF) in a horizontal saturated flow boiling water loop with a downward-facing heated surface in a macro-channel (40 mm × 10 mm cross-section) at atmospheric pressure. CHF models and correlations were evaluated against a new dataset spanning mass fluxes from and materials such as non-oxidized and oxidized copper and carbon steel. While several correlations accurately predicted CHF, many overlooked the effects of surface conditions and orientation, exposing gaps in existing methods. The study also examines radiation-induced surface activation (RISA) under electron beam and γ-ray irradiation. Results show γ-ray irradiation enhances CHF by up to 47% across metals, while electron beam irradiation has material-dependent effects: aluminum maintains stable CHF, but copper and silver exhibit an initial decrease followed by an increase at higher doses. This study provides insights of CHF behavior on downward-facing surfaces and for irradiated materials, offering guidance for selecting CHF models and informing nuclear safety applications, particularly in-vessel retention (IVR) strategies.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.