KIT reactor safety research for LWRs: Research lines, numerical tools, and prospects-Reference-Cited by-同舟云学术

KIT reactor safety research for LWRs: Research lines, numerical tools, and prospects

Published:2023-12 Issue: Volume:414 Page:112573
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Sanchez-Espinoza V.H.,Gabrielli F.,Imke U.,Zhang K.,Mercatali L.,Huaccho G.,Duran J.,Campos A.,Stakhanova A.,Murat O.,Mercan A.K.,Etcheto J.,Steinbrück M.,Stuckert J.,Gabriel S.,Ottenburger S.,Stieglitz R.,Tromm W.

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

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5. COBRA-EN, an Updated Version of the COBRA-3C/MIT Code for Thermal Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores;Basile,2010