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...

Deskribapen osoa

Gorde:
Xehetasun bibliografikoak
Egile nagusia: Nguyễn An Sơn, Trần Trung Nguyên, Trần Quốc Tuấn, Nguyễn Thị Minh Sang
Formatua: Journal article
Hizkuntza:Vietnamese
Argitaratua: 2024
Gaiak:
Sarrera elektronikoa:https://scholar.dlu.edu.vn/handle/123456789/3602
Etiketak: Etiketa erantsi
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Thư viện lưu trữ: Thư viện Trường Đại học Đà Lạt
Deskribapena
Gaia: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%.