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
- 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
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73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CONFIGURATION
CRITICAL ASSEMBLIES
Critical Assemblies
Criticality
MEASURED VALUES
Measured Values
NEUTRON FLUX
Neutron Flux
Neutron Velocity
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM 239
Plutonium
Plutonium 239
REACTIVITY
RESEARCH REACTORS
SOLUTIONS
THERMAL NEUTRONS
URANIUM 233
URANIUM 235
Uranium
Uranium 233
WATER