BEAVRS基准模型的cosRMC精细建模与临界测试验证

BEAVRS基准题是来自麻省理工学院(MIT)的基于商用压水堆全堆芯精细建模的国际基准模型,具有详细的实测数据,是由多种富集度燃料及控制棒组件组成的大型压水堆分析验证基准题。使用我国自主研发的蒙卡程序cosRMC对BEAVRS基准题进行精细建模,主要计算了热零功率(HZP)状态下的临界本征值、全堆功率分布和控制棒价值,并与实测值以及国际知名蒙卡程序MCNP,OpenMC,MC21等结果进行对比。HZP状态下,cosRMC临界本征值结果与MCNP计算结果相差仅7.1 pcm,符合较好；不同控制棒组件插入情况下的临界本征值与理论值1.000的偏差小于0.74%,控制棒价值结果与实测值误差小于100 pcm,计算精度与同类软件相当；此外还对比分析了全堆功率分布与实测值结果的吻合程度及误差产生原因。初步验证了cosRMC程序对复杂堆芯精细建模计算的可行性和准确性,为程序以后的应用及完善打下基础。

Meticulous modeling and verification on criticality calculation of BEAVRS benchmark by Monte-Carlo code cosRMC

BEAVRS is an international benchmark model based on the commercial PWR reactor with full-core meticulous modeling from MIT, and it has detailed measurement data. BEAVRS is a large 3D reactor benchmark for verification consisted of a variety of enrichment fuels and control rod assemblies. In this paper, cosRMC(a Monte Carlo code independently developed by China) is adopted in the detailed modeling of BEAVRS benchmark to calculate the critical eigenvalues, full reactor power distribution and the control rod worth with different control rod assenmblies inserted in the hot zero power(HZP) status. The results are compared with those by the internationally renowned programs MCNP, OpenMC and MC21. In the HZP status, the critical eigenvalue error between cosRMC and MCNP is just 7.1 pcm; the eigenvalues with different control rod assemblies inserted are calculated and the error is less than 0.74% compared with the theoretical error 1.000, and the difference between the calculated control rod worth and the measured value is less than 100 pcm, and the calculation accuracy agrees well with that of similar software; also the calculated full reactor power distribution is compared with the measured value and the reasons of error are analysed. The feasibility and accuracy of cosRMC in the complex core meticulous modeling are verified preliminarily, which lays a foundation for future applications and improvement.