In-vessel coolability and retention of a core melt-Reference-Cited by-同舟云学术

In-vessel coolability and retention of a core melt

Published:1997-06 Issue:1-3 Volume:169 Page:1-48
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Theofanous T.G.,Liu C.,Additon S.,Angelini S.,Kymäläinen O.,Salmassi T.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference58 articles.

1. AP600 Probabilistic Risk Assessment;AP600;DEAC03-90 SF18495,1994

2. An experimental study of natural convection in a volumetrically heated spherical pool bounded on top with a rigid wall;Asfia;Nucl. Eng. Des.,1996

3. Large scale experiments for core melt retention—BALI: corium pool thermalhydraulics SULTAN: boiling under natural convection;Bonnet,1994

4. High-temperature tensile and creep data for Inconel 600, 304 stainless steel And SA106B carbon steel;Chavez;Nucl. Eng. Des.,1994

Cited by 263 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Validation of CFD RANS of an internally heated natural convection in a hemispherical geometry;Nuclear Engineering and Design;2024-11

2. SAMPO-P: A prototypical scale low-temperature experiment on two-layer melt pool heat transfer in LWR lower head;Experimental Thermal and Fluid Science;2024-09

3. A Reynolds-averaged Navier–Stokes closure for steady-state simulations of Rayleigh–Bénard convection;Physics of Fluids;2024-08-01

4. Convective Heat Transfer in PWR, BWR, CANDU, SMR, and MSR Nuclear Reactors—A Review;Energies;2024-07-24

5. Experimental study of IVR-ERVC CHF limits for CAP1400;Progress in Nuclear Energy;2024-07