Core design and reactivity control optimization of small lead-cooled reactor LFR-180

Author:

Jin Xin,Sun Yubo,Guo HuiORCID,Chen Lixin,Jiang Xinbiao,Wang Lipeng,Gu Hanyang

Funder

National Natural Science Foundation of China

SASTIND

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

Reference31 articles.

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2. Overview of lead-cooled fast reactor activities[J];Alemberti;Prog. Nucl. Energy,2014

3. Allison, C.M., Hohorst, J.K., Ezzidi, A., et al. Development and preliminary assessment of the new ASYST-ISA integral analysis BEPU code using the PBF SFD-ST Bundle heating and melting experiment, a typical BWR Under Fukushima-Daiichi-Accident-Like Thermal Hydraulic Conditions and PWR for a Steam Line Break in the Containment[A]. 2020: 15–19.

4. Andriolo, L., Rineiski, A., Vezzoni, B., et al. An innovative methodology for evaluating core thermal expansion feedbacks in transient analyses[J]. 2015.

5. Aydogan, F. Advanced small modular reactors[A]. 见: I.L. Pioro. Handbook of Generation IV Nuclear Reactors[M]. Woodhead Publishing, 2016: 661–699.

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