Effective Reactor Cross Sections in MTR Fuel Assemblies

J. Halperin; J. O. Blomeke; D. A. Mrkvicka

doi:dx.doi.org/10.13182/NSE58-A25477

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Home / Publications / Journals / Nuclear Science and Engineering / Volume 3 / Number 4

Effective Reactor Cross Sections in MTR Fuel Assemblies

J. Halperin, J. O. Blomeke, D. A. Mrkvicka

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 395-402

Technical Paper / dx.doi.org/10.13182/NSE58-A25477

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Analyses of uranium, neptunium, and plutonium isotopes have been carried out on dissolved MTR fuel elements. Effective reactor cross sections computed from these measurements are in good agreement with differential cross-section measurements. In particular, effective cross-section values were found for U²³⁶ and U²³⁸ of 34 barns and 23 barns, respectively.