Study on the safety characteristics of fluoride-salt-cooled high-temperature advanced reactor

Author:

Lv Xindi,Zhang Dalin,Li Xinyu,Zhou Xingguang,Jiang Dianqiang,Su Guanghui,Tian Wenxi,Qiu Suizheng

Funder

National Key Research and Development Program of China

Ministry of Science and Technology of the People's Republic of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference15 articles.

1. Simulation of Partial and Complete Loss of Flow Accidents for GPWR using ATHLET Code;Abdel-Latif;International Journal of Thermofluids,2021

2. Andreades, C., Cisneros, A., Choi, J.K., Chong, A., Fratoni, M., Hong, S., Huddar, L., Huff, K., Krumwiede, D., Laufer, M., Munk, M., Scarlat, R., Zweibaum, N., Greenspan, E., Peterson, P., 2014. Technical Description of the “Mark 1” Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant. Department of Nuclear Engineering, University of California Berkeley.

3. Study of rod ejection accident at hot zero power condition in a PWR using RELAP5;El-Sahlamy;Progress in Nuclear Energy,2022

4. Molten-Salt-Cooled Advanced High-Temperature Reactor for Production of Hydrogen and Electricity;Forsberg;Nuclear Technology - NUCL TECHNOL,2003

5. Fratoni, M., 2008. Development and applications of methodologies for the neutronic design of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) (PhD Thesis). ProQuest Dissertations and Theses.

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