Technology Gap Analysis on Sodium-Cooled Reactor Fuel-Handling System Supporting Advanced Burner Reactor Development
Author:
Affiliation:
1. Argonne National Laboratory Nuclear Engineering Division, 9700 South Cass Avenue Building 208, Argonne, Illinois 60439
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/NT09-A4101
Reference60 articles.
Cited by 12 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
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3. On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor;Nuclear Engineering and Technology;2019-02
4. Four-bar linkage modeling and kinematics analysis of an in-vessel transfer system for Prototype Gen-IV Sodium-cooled Fast Reactor;Annals of Nuclear Energy;2018-03
5. Sodium-cooled fast reactor;Handbook of Generation IV Nuclear Reactors;2016
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