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首页> 外文期刊>Journal of nuclear science and technology >Measurements and Analyses of Angular Neutron Flux Spectra on Graphite and Lithium-Oxide Slabs Irradiated with 14.8 MeV Neutrons
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Measurements and Analyses of Angular Neutron Flux Spectra on Graphite and Lithium-Oxide Slabs Irradiated with 14.8 MeV Neutrons

机译:用14.8 MeV中子辐照的石墨和氧化锂平板上的角中子通量谱的测量和分析

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Angular neutron fluxes leaking from the surface of lithium-oxide and graphite slab assemblies have been measured with irradiation of D-T neutrons. The spectrum measurement was performed using the time-of-flight technique with an NE213 scintillation detector. The thicknesses of the slabs were 0.6 to 5 mean free path for 14.8 MeV neutrons, and the measured leaking angles of the angular fluxes were 0.0°, 12.2°, 24.9°, 41.8° and 66.8°. The experimental results have been compared with the results calculated by the continuous energy Monte Carlo transport code MCNP, using the data in the JENDL-3PR1, -3PR2, and ENDF/B-V nuclear data files. The comparisons between the experimental and calculated results show that the data of 7Li in JENDL-3PR2 is improved for the secondary emission spectra of the 4.63 MeV level and (n, 2n) reactions; the angular distributions of 3rd- and 4th-level inelastic reactions of C in the JENDLs are questionable. The thickness dependences for high energy neutrons also suggest that the total cross section of 7Li and the elastic cross sections of C are slightly inadequate.
机译:从D-T中子辐照测量了从氧化锂和石墨平板组件表面泄漏的角中子通量。使用飞行时间技术和NE213闪烁检测器进行光谱测量。平板的厚度为14.8 MeV中子的平均自由程为0.6至5,测得的角通量泄漏角为0.0°,12.2°,24.9°,41.8°和66.8°。使用JENDL-3PR1,-3PR2和ENDF / B-V核数据文件中的数据,将实验结果与连续能量蒙特卡洛输运代码MCNP计算的结果进行了比较。实验结果与计算结果的比较表明,JENDL-3PR2中7Li的数据对于4.63 MeV水平的二次发射光谱和(n,2n)反应得到了改善。 JENDL中C的3级和4级非弹性反应的角分布是可疑的。高能中子的厚度依赖性还表明,7Li的总横截面和C的弹性横截面略有不足。

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