Subcritical Measurements Using the 252Cf Source-Driven Neutron Noise Analysis Method
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Instrumentation and Controls Division
This paper describes recent measurements of the subcritical neutron multiplication factor using the 252Cf source-driven neutron noise analysis method. This work was supported by a program of collaboration between the United States Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan related to the development of fast breeder technology. The experiment reported consists of a configuration of two interacting tanks of uranyl nitrate aqueous solution with different uranium concentrations in each tank. The 252Cf-source-driven neutron noise analysis method obtains the subcriticality from the signals of three detectors: the first, a parallel plate ionization chamber with 252Cf electroplated on one of its plates that is located in or near the system containing the fissile material, and produces an electrical pulse for every spontaneous fission that occurs and thereby serves as a timed source of fission neutrons; and the second and third detectors that are placed in or near the system containing fissile material and serve to detect particles from the fission chain multiplication process.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Instrumentation and Controls Division
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Facilities, Fuel Cycle, and Test Programs
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5665180
- Report Number(s):
- CONF-860906-1; ON: DE86005592
- Resource Relation:
- Conference: ANS Topical Meeting on Reactor Physics and Safety , Saratoga Springs, NY (United States), 17 Sep 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
LMFBR TYPE REACTORS
REACTOR NOISE
SUBCRITICALITY
AQUEOUS SOLUTIONS
CALIFORNIUM 252
MULTIPLICATION FACTORS
URANYL NITRATES
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BREEDER REACTORS
CALIFORNIUM ISOTOPES
DISPERSIONS
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
FAST REACTORS
FBR TYPE REACTORS
HEAVY NUCLEI
ISOTOPES
LIQUID METAL COOLED REACTORS
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEI
OXYGEN COMPOUNDS
RADIOISOTOPES
REACTORS
SOLUTIONS
URANIUM COMPOUNDS
URANYL COMPOUNDS
YEARS LIVING RADIOISOTOPES
Nuclear Criticality Safety Program (NCSP)
United States Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan
Fast Breeder Technology
Fissile Material
Pulsed Neutron
Rossi-α
Uranium Metal
Californium Neutron
Cross-Power Spectral Density (CPSD)
Monte Carlo Calculations
210500* - Power Reactors
Breeding