Simulation of melt jet breakup experiments by JASMINE with an empirical correlation for melt particle size distribution-Reference-Cited by-同舟云学术

Simulation of melt jet breakup experiments by JASMINE with an empirical correlation for melt particle size distribution

Published:2016-03-04 Issue:10 Volume:53 Page:1608-1621
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Moriyama Kiyofumi¹,Park Hyun Sun¹

Affiliation:

1. Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), Pohang, Gyeongsangbuk-do, Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2016.1146636

Reference29 articles.

1. OECD/NEA. OECD workshop on ex-vessel debris coolability summary and recommendations. Paris (France): OECD/NEA/CSNI; 2000. (NEA/CSNI/R(2000)14).

2. Particulate debris formation by breakup of melt jets: Main objectives and solution perspectives

3. OECD/NEA. OECD research program on fuel-coolant interaction: steam explosion resolution for nuclear applications – SERENA, final report. Paris (France): OECD/NEA/CSNI; 2007. (NEA/CSNI/R(2007)11).

4. OECD/NEA. OECD/SERENA project report: summary and conclusions. Paris (France): OECD/NEA; 2015. (NEA/CSNI/R(2014)15).

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