All the calculations were done for the chosen benchmark BN-600 reactor core. The report contains short description of the applied codes and nuclear data libraries used. The computer codes used for the cell calculations, i.e. calculations of effective cross sections applied Monte Carlo ...
基准快堆例题BN-600对VisualBUS4.2的测试%Testing of VisualBUS4.2 with fast reactor test benchmark BN-600快堆基准例题中子学VisualBUS4.2使用国际原子能机构的基准快堆例题BN-600对大型集成多功能中子学计算分析系统VisualBUS4.2进行了测试.与国际上其他单位的程序和数据库计算结果对比分析,其中有效增值因子(keff),...
In 1999, the IAEA has initiated a Coordinated Research Project on Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR Reactivity Effects. Three benchmark models representing different modifications of the BN-600 fast reactor have been sequentially established and analyzed, in...
Assessing reactor physics codes capabilities to simulate fast reactors on the example of the BN-600 Benchmark This work aims to assess the capabilities of reactor physics codes (initially validated for thermal reactors) to simulate fast sodium cooled reactors. The ... V Ivanov,J Bousquet - 《Ker...
使用国际原子能机构的基准快堆例题BN-600对大型集成多功能中子学计算分析系统VisualBUS4.2进行了测试.与国际上其他单位的程序和数据库计算结果对比分析,其中有效增值因子(keff),燃料多普勒系数(kDfue1),径向膨胀系数(Rrad),轴向膨胀系数Rax)和有效缓发中子份额(βeff)的计算结果均介于其他单位测试值之间,验证了算法与各...
Three benchmark models representing different modifications of the BN-600 fast reactor have been sequentially established and analyzed, including a hybrid core with highly enriched uranium oxide and MOX fuel, a full MOX core with weapons-grade plutonium, and a MOX core with plutonium and minor ...
The BFS-62-3A critical benchmark experiment was set-up as a mock-up of the BN-600 reactor core with (U,Pu) O fuel of 17% Pu content and stainless-steel reflectors. It was operated to measure the effective multiplication factor, spectral indices, radial fission rate distributions, control...
Results from this model were verified using published results of benchmark problems that utilized diffusion or transport theories in calculation and found acceptable. The maximum difference was about 4% for multiplication factor, 1% for control rod worth, and 2.6% for radial power distribution. The ...
Assessing reactor physics codes capabilities to simulate fast reactors on the example of the BN-600 Benchmark This work aims to assess the capabilities of reactor physics codes (initially validated for thermal reactors) to simulate fast sodium cooled reactors. The ... V Ivanov,J Bousquet - 《Ker...