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The ENDF/B-IV Representation of the Uranium-238, Total Neutron Cross Section in the Resolved Resonance Energy Region

 

作者: SaussureG. de,   OlsenD. K.,   PerezR. B.,  

 

期刊: Nuclear Science and Engineering  (Taylor Available online 1976)
卷期: Volume 61, issue 4  

页码: 496-506

 

ISSN:0029-5639

 

年代: 1976

 

DOI:10.13182/NSE76-A14486

 

出版商: Taylor&Francis

 

数据来源: Taylor

 

摘要:

AbstractThe ENDF/B-IV prescription fails to represent correctly the238U total (and scattering) cross section between the levels of the resolved range. We show how this representation can be improved by properly accounting for the contribution of levels outside the resolved region to the cross section at energies inside the resolved region, and by substituting the more precise multi-level Breit-Wigner formula for the presently used single-level formula. We illustrate the importance of computing accurately the minima in the total cross section by comparing values of the self-shielded capture resonance integral computed with ENDF/B-IV and with a more accurate cross-section model.

 

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