Average Total Neutron Cross Section of ~(233)U, ~(235)U and ~(239)Pu from ORELA Transmission Measurements and Statistical Model Analysis of the Data

机译：平均总中子截面〜（233）u，〜（235）u和〜（239）pu从orela传输测量和数据的统计模型分析

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摘要

The average total neutron cross sections of ~(233)U, ~(235)U, and ~(239)Pu were obtained from transmission measurements in the unresolved resonance region up to several hundred keV neutron energy. The method used for the calculation of the self-shielding effect is described. A statistical model analysis of the results was performed and the s-, p- and d-wave neutron strength functions were obtained.

机译：从未解决的共振区域中的透射测量获得高达几百KeV中子能量的透射测量，获得〜（233）U，〜（235）U和〜（239）PU的平均总中子横截面。描述了用于计算自屏蔽效果的方法。进行了结果的统计模型分析，获得了S-，P和D波中子强度功能。

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《International Conference on Nuclear Data for Science and Technology》|2002年||共4页
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作者
Herve Derrien; Klaus H. Guber; John A. Harvey; Nancy M. Larson; Luiz C. Leal;
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原文格式 PDF
正文语种
中图分类 O57-532;
关键词
total cross section; statistical model; strength function; uranium 233; uranium 235; plutonium 239;

机译：总横截面;统计模型;强度功能;铀233;铀235;钚239;

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1. MODELING THE DETECTION OF DELAYED NEUTRON SIGNATURES IN MCNP6 AND COMPARISONS WITH MEASUREMENTS OF ~(233)U, ~(235)U, AND ~(239)PU [J] . M. T. ANDREWS, J. T. GOORLEY, E. C. CORCORAN, Nuclear Technology . 2014,第3期

机译：对MCNP6中延迟中子信号检测的建模及其与〜（233）U，〜（235）U和〜（239）PU测量值的比较
2. 233U, 235U, and 239Pu and the Spontaneous Fission of 252Cf]]> [J] . A. S. Vorobyev, O. A. Shcherbakov, A. M. Gagarski, Bulletin of the Russian Academy of Sciences. Physics . 2018,第10期

机译：<！[CDATA [迅速裂变中子从热中子诱导裂变的角度和能量分布<上标> 233 U，<上标> 235 U，以及<上标> 239 PU和<上标> 252 CF]的自发裂变]>
3. 233U, 235U, and 239Pu]]> [J] . I. S. Guseva, A. M. Gagarski, V. E. Sokolov, Physics of atomic nuclei . 2018,第4期

机译：<！[CDATA [CDATA [CDATA [中子中子中子 - 中子角度相关性在慢中子诱导的<上标> 233 U，<上标> 235 U，<上标> 239 中的中子中子角度相关性 pu]]>
4. Average Total Neutron Cross Section of ~(233)U, ~(235)U and ~(239)Pu from ORELA Transmission Measurements and Statistical Model Analysis of the Data [C] . Herve Derrien, Klaus H. Guber, John A. Harvey, International Conference on Nuclear Data for Science and Technology . 2002

机译：平均总中子截面〜（233）u，〜（235）u和〜（239）pu从orela传输测量和数据的统计模型分析
5. Energy Dependence of Fission Product Yields from 235 U, 238U, and 239Pu for Incident Neutron Energies Between 0.5 and 14.8 MeV [D] . Gooden, Matthew Edgell 2014

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7. NEUTRON TOTAL CROSS SECTIONS OF 235U FROM TRANSMISSION MEASUREMENTS IN THE ENERGY RANGE 2 keV to 300 keV AND STATISTICAL MODEL ANALYSIS OF THE DATA [O] . Derrien, H. 2000

机译：能量范围2 keV至300 keV的输电测量中的235U的中子总截面和数据的统计模型分析
8. Average Total Neutron Cross Section OF 233U, 235U AND 239Pu from ORELA Transmission Measurements and Statistical Analysis of the Data. [R] . Derrien, H. 2001

机译：ORELa传输测量和数据统计分析的233U，235U和239pu的平均总中子截面。

Average Total Neutron Cross Section of ~(233)U, ~(235)U and ~(239)Pu from ORELA Transmission Measurements and Statistical Model Analysis of the Data

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