Khảo sát thông lượng neutron nhiệt của lò phản ứng hạt nhân OPR1000 với hệ mô phỏng Cosi OPR1000

OPR1000 nuclear reactor is pressurized water reactor, which uses thermal neutron to keep up nuclear fission. Therefore, thermal neutron flux is very important for investigating the design, construction and operation of such type of nuclear reactor. This paper introduces some research results of t...

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Príomhúdar: Nguyễn An Sơn, Trần Trung Nguyên, Trần Quốc Tuấn, Nguyễn Thị Minh Sang
Formáid: Journal article
Teanga:Vietnamese
Foilsithe: 2024
Ábhair:
Rochtain Ar Líne:https://scholar.dlu.edu.vn/handle/123456789/3602
Clibeanna: Cuir Clib Leis
Gan Chlibeanna, Bí ar an gcéad duine leis an taifead seo a chlibeáil!
Thư viện lưu trữ: Thư viện Trường Đại học Đà Lạt
Cur Síos
Achoimre:OPR1000 nuclear reactor is pressurized water reactor, which uses thermal neutron to keep up nuclear fission. Therefore, thermal neutron flux is very important for investigating the design, construction and operation of such type of nuclear reactor. This paper introduces some research results of thermal neutron flux calculation and simulation of OPR1000 nuclear reactor at subcritical, critical and super-critical operating states. Simulated results have been carried out on OPR1000 Core Simulator. The results showed a good correlation between the theoretical calculation and the simulation with the deviation smaller than 2,1%.