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Determination of $$\overline{η}$$ by Comparison of $$\overline{η}$$σ for U235 and Pu239 with $$\overline{η}$$oa for U235 in a Flux Critical Assembly Distribution

Technical Report ·
DOI:https://doi.org/10.2172/4179933· OSTI ID:4179933
 [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The values of $$\overline{η}$$ for U233 and $$\overline{η}$$ for Pu239 have been determined by a reactivity coefficient measurement. An aqueous solution of the isotope was introduced axially into a critical cylindrical annular flux trap reactor, and the resulting reactor change measured by period determinations. From these data the ratio $$\overline{η}$$σax/$$\overline{η}$$σa(U235) was obtained. Using recently measured values of σa(U235) and η for U235 in this ratio gives the thermal value of 2.308 ± 0.040 for $$\overline{η}$$ of U233 and 1.995 ± 0.053 for $$\overline{η}$$ of Pu239. Correction to a neutron velocity of 2200 m/sec by using the appropriate g-factor gives a value of 2.308 ± 0.040 for η of U233 and 2.044 ± 0.054 for η of Pu239.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-14-017345
OSTI ID:
4179933
Report Number(s):
CF-60-4-11
Country of Publication:
United States
Language:
English