Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap-Reference-Cited by-同舟云学术

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Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap

Published:2006-04 Issue:1 Volume:154 Page:13-40
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Kim Yong H.¹,Kim Sung J.¹,Suh Kune Y.¹,Rempe Joy L.²,Cheung F. Bill³,Kim Sang B.⁴

Affiliation:

1. Seoul National University San 56-1 Sillim-dong, Gwanak-gu, Seoul 151-742, Korea

2. Idaho National Laboratory, Idaho Falls, Idaho 83415

3. The Pennsylvania State University University Park, Pennsylvania 16802

4. Korea Atomic Energy Research Institute, Yuseong Daejeon 305-600, Korea

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT06-A3715

Reference61 articles.

1. External cooling of a reactor vessel under severe accident conditions

2. Debris interactions in reactor vessel lower plena during a severe accident I. Predictive model

3. Debris interactions in reactor vessel lower plena during a severe accident II. Integral analysis

4. Effects of buoyancy on the critical heat flux in forced convection

5. Effects of heater surface orientation on the critical heat flux—I. An experimental evaluation of models for subcooled pool boiling

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1. Effect of the heat transfer liquid fin on critical heat flux enhancement under ERVC condition;International Journal of Heat and Mass Transfer;2020-04

2. Heat transfer performance of downward-facing carbon and stainless steel surfaces;International Communications in Heat and Mass Transfer;2020-04

3. Critical heat flux in various inclined rectangular straight surface channels;Experimental Thermal and Fluid Science;2014-01

4. Surface engineering for phase change heat transfer: A review;MRS Energy & Sustainability;2014-01

5. Development of CHF models for inner and outer RPV gaps in a meltdown severe accident;Nuclear Engineering and Design;2013-12

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