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Sensitivity of Calculations of 252Cf-Source-Driven Noise Analysis Measurements to Cross-Sections for Aqueous Fissile Plutonium Solutions

Conference ·
OSTI ID:10128614
 [1];  [2];  [3]
  1. Oak Ridge Inst. for Science and Education (ORISE), Oak Ridge, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Univ. of Tennessee, Knoxville, TN (United States)
Previous experiments have shown large changes in noise-measured parameters for small changes in the measured configuration of fissile material. The sensitivity was investigated by the Monte Carlo code KENO-NR. This code calculates the noise data from the 252Cf-source-driven neutron noise measurement. These calculations have shown that noise-measured quantities are more sensitive to cross sections than the neutron multiplication factor by a factor of as much as ~50 for this fissile plutonium solution. This increased sensitivity means that for verifying calculational methods, a subcritical experiment at a k ~ 0.9 by the 252Cf-source-driven noise analysis method is more useful than experiments at k = 1.
Research Organization:
Oak Ridge Inst. for Science and Education (ORISE), Oak Ridge, TN (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
10128614
Report Number(s):
CONF-940407--7; ON: DE94007420
Country of Publication:
United States
Language:
English