Calculations of the Weale experiment using modified ENDF/B-IV238U cross sections

M. Segev, A.D. Krumbein, M. Lemanska, J.J. Wagschal, A. Yaari

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review


Describes how the 238U cross sections may be more accurately calculated for use in the Weale experiment (1961) to measure neutron reaction rates.
Original languageEnglish
Title of host publicationTrans. Am. Nucl. Soc. (USA)
Subtitle of host publicationConference: ANS annual meeting, San Diego, CA, USA, 18 Jun 1978
Place of PublicationUSA
Pages37 - 8
Number of pages2
StatePublished - 1978

Bibliographical note

<sup>238</sup>U cross sections;neutron reaction rates;


  • fission of uranium
  • fission reactor theory and design
  • neutron transport theory
  • neutron-nucleus reactions
  • nuclei with mass number 220 or higher


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