Preliminary Investigation of 252Cf-Driven Neutron Noise Analysis for Subcritical Fuel Solution Systems
Conference
·
OSTI ID:6489679
- 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
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050700* -- Nuclear Fuels-- Fuels Production & Properties
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
ENERGY SOURCES
EVEN-EVEN NUCLEI
EXPERIMENTAL REACTORS
FUELS
Fast Flux Test Facility Reactor
Fissile Material
Fuel Elements
Fuel Solution Tanks
HEAVY NUCLEI
ISOTOPES
Light-Water Moderated
Los Alamos National Laboratory SHEBA Facility
MATERIALS
NEUTRON SOURCES
NUCLEAR FUELS
NUCLEI
Nuclear Criticality Safety Program (NCSP)
Oak Ridge Research Reactor
PARTICLE SOURCES
RADIATION SOURCES
RADIOISOTOPES
REACTIVITY
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
Reflected Lattice
SPENT FUEL STORAGE
SPENT FUELS
STORAGE
SUBCRITICAL ASSEMBLIES
YEARS LIVING RADIOISOTOPES
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
ENERGY SOURCES
EVEN-EVEN NUCLEI
EXPERIMENTAL REACTORS
FUELS
Fast Flux Test Facility Reactor
Fissile Material
Fuel Elements
Fuel Solution Tanks
HEAVY NUCLEI
ISOTOPES
Light-Water Moderated
Los Alamos National Laboratory SHEBA Facility
MATERIALS
NEUTRON SOURCES
NUCLEAR FUELS
NUCLEI
Nuclear Criticality Safety Program (NCSP)
Oak Ridge Research Reactor
PARTICLE SOURCES
RADIATION SOURCES
RADIOISOTOPES
REACTIVITY
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
Reflected Lattice
SPENT FUEL STORAGE
SPENT FUELS
STORAGE
SUBCRITICAL ASSEMBLIES
YEARS LIVING RADIOISOTOPES