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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| 第一著者: | |
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| フォーマット: | Journal article |
| 言語: | Vietnamese |
| 出版事項: |
2024
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| 主題: | |
| オンライン･アクセス: | https://scholar.dlu.edu.vn/handle/123456789/3602 |
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| Thư viện lưu trữ: | Thư viện Trường Đại học Đà Lạt |
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| 要約: | 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%. |
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