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Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data
From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date:
November 29, 1951
Creator:
Shapiro, Mathew; Preiser, Stanley & Young, Gale
System:
The UNT Digital Library