Four-bar linkage modeling and kinematics analysis of an in-vessel transfer system for Prototype Gen-IV Sodium-cooled Fast Reactor

Author:

Lim Dong-Won,Lee Jae-Han,Kim Sung-Kyun

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Generation-IV nuclear power: a review of the state of the science;Abram;Energy Policy,2008

2. Adams, E., Gray, J., Shipley, D., Bates, P., 1986. Fuel handling operations and maintenance experience on the prototype fast reactor (PFR) Dounreay. In: Engineering Developments in Reactor Refuelling.

3. Tests carried out for SNR-300 handling and the influence of test results in view of handling equipment design;Babilas;Trans. Am. Nucl. Soc.,1975

4. Fuel and special handling facilities for Phenix;Benoist;Nucl. Eng. Int.,1971

5. Superphénix 1 primary handling system fabrication and testing;Branchu;Nucl. Technol.,1985

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