• In this thesis, stress analysis and calculation for a large oxidized reactor considering are made by using ANSYS FEM code.

    本课题用ANSYS软件对某大型氧化反应器流固耦合进行了有限元应力分析计算。

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  • A computer code FDKR and its associated data library AF-DCDLIB have been developed for fusion-fission hybrid reactor radioactivity calculations.

    研制了聚变一裂变混合堆放射性计算程序fdkr和配套的衰变链数据库af—DCDL—IB。

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  • The function of reactor shutdown system can be simulated by the code to calculate the operating parameters after accidental shutdown.

    程序中还引入停堆保护计算模块以模拟反应堆事故停堆后的运行工况。

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  • SCAS is the source term code to calculate steam activation products in secondary loop of reactor, which is developed by Nuclear Power Institute of China.

    SCAS是中国核动力研究设计院编制的反应堆二回路蒸汽活化产物源项程序。

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  • A integrated code for in core fuel management was formed by combining this code with a reactor physics code.

    并可与相应的堆物理计算程序构成一个完整的堆芯燃料管理程序。

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  • They are the natural circulation flow analysis code (MC-FLOW), the core thermal hydraulic analysis code (MC-THAS) and the pulsed reactor transient analysis code (MC-TRAN).

    它包括脉冲堆自然循环分析程序(MC-FLOW)、堆芯热工水力分析程序(MC-THAS)和脉冲堆瞬态分析程序(MC-TRAN)。

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  • The code package of uranium hydride zirconium reactor physics calculation is established.

    建立了一套铀氢锆堆物理计算软件包。

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  • The code package of uranium hydride zirconium reactor physics calculation is established.

    建立了一套铀氢锆堆物理计算软件包。

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