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Development and validation of the code COUPLE3.0 for the coupled analysis of neutron transport and burnup in ADS 被引量:2
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作者 Lu Zhang Yong-Wei Yang +2 位作者 Yuan-Guang Fu De-Liang Fan Yu-Cui Gao 《Nuclear Science and Techniques》 SCIE CAS CSCD 2018年第9期139-147,共9页
The analysis of the fuel depletion behavior is critical for maintaining the safety of accelerator-driven subcritical systems(ADSs). The code COUPLE2.0 coupling 3-D neutron transport and point burnup calculation was de... The analysis of the fuel depletion behavior is critical for maintaining the safety of accelerator-driven subcritical systems(ADSs). The code COUPLE2.0 coupling 3-D neutron transport and point burnup calculation was developed by Tsinghua University. A Monte Carlo method is used for the neutron transport analysis, and the burnup calculation is based on a deterministic method. The code can be used for the analysis of targets coupled with a reactor in ADSs. In response to additional ADS analysis requirements at the Institute of Modern Physics at the Chinese Academy of Sciences, the COUPLE3.0 version was developed to include the new functions of(1) a module for the calculation of proton irradiation for the analysis of cumulative behavior using the residual radionuclide operating history,(2) a fixed-flux radiation module for hazard assessment and analysis of the burnable poison, and(3) a module for multi-kernel parallel calculation, which improves the radionuclide replacement for the burnup analysis to balance the precision level and computational efficiency of the program. This paper introduces thevalidation of the COUPLE3.0 code using a fast reactor benchmark and ADS benchmark calculations. Moreover,the proton irradiation module was verified by a comparison with the analytic method of calculating the210 Po accumulation results. The results demonstrate that COUPLE3.0 is suitable for the analysis of neutron transport and the burnup of nuclides for ADSs. 展开更多
关键词 COUPLE3.0 NEUTRON transport BURNUP Accelerator-driven SUBCRITICAL system
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5-1 Introduction to Code System COUPLE3.0 for Neutron Transport and Nuclides Burn-up Analyses
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作者 Yang Yongwei Zhang Lu Fu Yuanguang 《IMP & HIRFL Annual Report》 2015年第1期221-222,共2页
The code system COUPLE2.0[1] was developed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, which can be used for coupled neutron transport and nuclide burn-up analyses of Accelerat... The code system COUPLE2.0[1] was developed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, which can be used for coupled neutron transport and nuclide burn-up analyses of Accelerator Driven sub- critical reactor System(ADS). The Institute of Modern Physics, Chinese Academy of Sciences imported the code system in 2014, and developed the version COUPLE3.0 according to the requirements of new function and preliminary verifications based on the fast reactor and ADS benchmarks were done. 展开更多
关键词 NUCLIDES BURN-UP ANALYSES
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