Prompt ν-values of 235U and 239Pu in some fast reactor spectra

L. Widén, H. Condé
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Abstract

The averaged number of prompt neutrons per 335sU and 239Pu fission have been measured in fast and thermalized neutron fluxes at the fast zero-power reactor (FRO) at Studsvik, Sweden. The measurements were made with three different reactor cores giving median fission energies for 235U (core centre) of 50, 170 and 240 keV. The spectrum averaged v data were compared with the corresponding thermal ν data. The ν-value of the spontaneous fission of 252Cf was used as an intermediate standard. The fission samples were placed in neutron beams extracted from the reactor cores and a large liquid scintillator was used as the fission neutron detector. The experiment also included relative fission rate measurements, 238U/235U, for the three reactor cores.

The results are compared with calculated relative ν-values deduced from different sets of recently evaluated fission cross section and ν-data and from different assumptions concerning the reactor neutron spectra. Within the experimental one standard deviation errors of 1·5 and 2 per cent for 235U and 239Pu a good agreement was obtained between the experimental and calculated data assuming ν-values in the fission resonance region equal to ν at thermal energy.

某些快堆光谱中235U和239Pu的提示ν值
在瑞典Studsvik的快速零功率反应堆(FRO)上,用快中子通量和热中子通量测量了335sU和239Pu裂变的平均提示中子数。用三个不同的堆芯进行了测量,得出235U(堆芯中心)的裂变能中值分别为50,170和240kev。将光谱平均v数据与相应的热ν数据进行了比较。252Cf的自发裂变ν值作为中间标准。裂变样品被放置在从反应堆堆芯提取的中子束中,并使用一个大型液体闪烁体作为裂变中子探测器。实验还包括对三个反应堆堆芯的相对裂变率(238U/235U)的测量。将计算结果与从不同组最近评估的裂变截面和ν数据以及对反应堆中子能谱的不同假设推导出的相对ν值进行了比较。235U和239Pu的实验误差分别为1.5%和2%,在假设裂变共振区的ν值等于ν at热能的情况下,实验数据与计算数据吻合较好。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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