首页> 外文会议>International conference on the physics of reactors;PHYSOR 2010 >APPLICATION OF GLOBAL SENSITIVITY ANALYSIS APPROACH TO EXERCISE 1-2 OF THE OECD LWR UAM BENCHMARK
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APPLICATION OF GLOBAL SENSITIVITY ANALYSIS APPROACH TO EXERCISE 1-2 OF THE OECD LWR UAM BENCHMARK

机译:全球敏感性分析方法在OECD LWR UAM基准练习1-2中的应用

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This paper is three fold. In the first part, continuous energy Monte Carlo calculations are performed as reference solutions to the test problems of Exercise 2 of Phase 1 (1-2), "Lattice Physics", of the OECD LWR UAM Benchmark. Using an automated tool for the generation of temperature-dependent continuous-energy cross section libraries, developed at the Pennsylvania State University (PSU), reference solutions are obtained using the different available Nuclear Data Libraries (NDL). These reference solutions provide the required data to the participants of the OECD UAM Benchmark.The second part of this paper focuses on the comparison between a new thermal scattering cross section library and the MCNP5 built-in thermal libraries. This gives the possibility of performing MCNP5 criticality calculations at the correct moderator temperature and improving the accuracy of the calculation.In the final part of the paper, global sensitivity analysis is applied to the modeling of nuclear reactor calculations for better model understanding. Specifically, it is investigated how much criticality conditions are affected by uncertainties in various inputs, including nuclear cross-sections, at different energies, from several isotopes in the fuel, the absorber and the moderator. The sensitivity analysis uses the Sobol' and Jansen formulas, which allow us to estimate, for each uncertain input, its main effect, its total effect (i.e. the overall effect, which includes all the interactions, at any order, with all the other uncertain inputs), and all two-way interactions among all possible pairs of uncertain inputs. The sensitivity analysis consists of a number of model simulations, which are performed using MCNP5.
机译:这篇论文是三折的。在第一部分中,进行了连续能量蒙特卡洛计算,作为对经合组织轻水堆UAM基准的阶段1(1-2)的练习2(“格点物理”)的测试问题的参考解决方案。使用宾夕法尼亚州立大学(PSU)开发的用于生成温度相关的连续能量截面库的自动工具,可以使用不同的可用核数据库(NDL)获得参考解决方案。这些参考解决方案为OECD UAM基准测试的参与者提供了所需的数据。 本文的第二部分着重于新的热散射截面库与MCNP5内置热库之间的比较。这提供了在正确的慢化剂温度下执行MCNP5临界度计算的可能性,并提高了计算的准确性。 在本文的最后部分,将全局敏感性分析应用于核反应堆计算的建模,以更好地理解模型。具体而言,研究了燃料,吸收器和减速器中的几种同位素在不同能量下的各种输入(包括核横截面)的不确定性对关键条件的影响程度。敏感性分析使用Sobol'和Jansen公式,这使我们能够针对每个不确定的输入估算其主要作用,其总作用(即整体作用,包括任何顺序的所有相互作用以及所有其他不确定的作用)输入),以及所有可能的不确定输入对之间的所有双向交互作用。灵敏度分析包括许多模型仿真,这些仿真使用MCNP5进行。

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