Preliminary Investigation of ²⁵²Cf-Driven Neutron Noise Analysis for Subcritical Fuel Solution Systems

Conference · Thu Jan 01 00:00:00 EST 1981

OSTI ID:6489679

Mihalczo, J. T. ^[1]; Kryter, R. C. ^[1]; King, W. T. ^[1]

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1. 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

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CALIFORNIUM 252
NEUTRON SOURCES
NUCLEAR FUELS
REACTIVITY
SPENT FUEL STORAGE
SUBCRITICAL ASSEMBLIES
SPENT FUELS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CALIFORNIUM ISOTOPES
ENERGY SOURCES
EVEN-EVEN NUCLEI
EXPERIMENTAL REACTORS
FUELS
HEAVY NUCLEI
ISOTOPES
MATERIALS
NUCLEI
PARTICLE SOURCES
RADIATION SOURCES
RADIOISOTOPES
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
STORAGE
YEARS LIVING RADIOISOTOPES
Nuclear Criticality Safety Program (NCSP)
Light-Water Moderated
Reflected Lattice
Oak Ridge Research Reactor
Fuel Elements
Fast Flux Test Facility Reactor
Los Alamos National Laboratory SHEBA Facility
Fissile Material
Fuel Solution Tanks
050700* - Nuclear Fuels- Fuels Production & Properties
050800 - Nuclear Fuels- Spent Fuels Reprocessing
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors