Preliminary Investigation of 252Cf-Driven Neutron Noise Analysis for Subcritical Fuel Solution Systems
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
A method for determining the reactivity of highly subcritical systems of fissile material, using neutron-noise power spectral densities in conjunction with a 252Cf source, had previously been tested in two fast reactor critical assemblies (a mockup of the Fast Flux Test Facility reactor and unreflected enriched uranium metal assemblies) and one thermal reactor (a light-water moderated and reflected lattice of Oak Ridge Research Reactor fuel elements). The last-mentioned test demonstrated the effectiveness of the method in water-moderated systems and thereby prompted the present study of its application to facilities for fuel preparation, reprocessing, and storage. To investigate the applicability of this method to facilities for fuel preparation, reprocessing, and storage, limited experiments were performed with a uranyl fluoride solution. The Los Alamos National Laboratory SHEBA facility, an unreflected cylindrical tank (56 cm diam), was partially filled with a solution containing 5 wt % 235U-enriched uranium (rho (U) approx. 1 g/cc, H/U atomic ratio approx. 550). The tank had a central 5-cm-diam axial hole in which the 252Cf source was placed at the midpoint of the solution. Measurements were performed at various solution heights from 60% of the critical height to near-critical height (approx. 36 cm).
- 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)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6489679
- Report Number(s):
- CONF-810606-41; ON: DE81023217; TRN: 81-011105
- Resource Relation:
- Conference: American Nuclear Society Annual Meeting, Miami Beach, FL (United States), 7 Jun 1981
- Country of Publication:
- United States
- Language:
- English
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