A portable measurement system for subcriticality measurements by the CF-source-driven neutron noise analysis method

Conference · Mon Feb 01 00:00:00 EST 1988 · IEEE Trans. Nucl. Sci.; (United States)

OSTI ID:6913201

Mihalczo, J T; Ragan, G E; Blakeman, E D

A portable measurement system consisting of a personal computer used as a Fourier analyzer and three detection channels (with associated electronics that provide the signals to analog-to-digital (A/D) convertors) has been assembled to measure subcriticality by the /sup 252/Cf-source-driven neutron noise analysis method. The /sup 252/Cf-source-driven neutron noise analysis method for obtaining the subcritical neutron multiplication factor of a configuration of fissile material requires measurement of the frequency-dependent cross-power spectral density (CPSD), G/sub 23/(..omega..), between a pair of detectors (Nos. 2 and 3) located in or near the fissile material and CPSDs G/sub 12/(..omega..) and G/sub 13/(..omega..) between these same detectors and a source of neutrons emanating from an ionization chamber (No. 1) containing /sup 252/Cf, also positioned in or near the fissile material. The auto-power spectral density (APSD), G/sub 11/(..omega..), of the source is also required. A particular ratio of spectral densities, G/sub 12//sup */G/sub 13//G/sub 11/G/sub 23/ (/sup */ denotes complex conjugation), is then formed. This ratio is related to the subcritical neutron multiplication factor and is independent of detector efficiencies.

• Research Organization: Instrumentation and Controls Div., Oak Ridge National Lab., P.O. Box X, Oak Ridge, TN (US)
• OSTI ID: 6913201
• Report Number(s): CONF-871006-
• Journal Information: IEEE Trans. Nucl. Sci.; (United States), Vol. 35:1; Conference: 34. nuclear science symposium and 19. nuclear power systems symposium, San Francisco, CA, USA, 21 Oct 1987
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
REACTOR MONITORING SYSTEMS
DESIGN
SUBCRITICALITY
NEUTRON DETECTION
CALIFORNIUM 252
COMPUTER ARCHITECTURE
FOURIER ANALYSIS
HELIUM 3
HFIR REACTOR
IONIZATION CHAMBERS
NEUTRON DETECTORS
NEUTRON REACTIONS
NOISE
PERSONAL COMPUTERS
PORTABLE EQUIPMENT
POWER DENSITY
REACTOR SAFETY
RECORDING SYSTEMS
SIGNAL CONDITIONERS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
CALIFORNIUM ISOTOPES
COMPUTERS
DETECTION
DIGITAL COMPUTERS
ELECTRONIC CIRCUITS
ENRICHED URANIUM REACTORS
EQUIPMENT
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HADRON REACTIONS
HEAVY NUCLEI
HELIUM ISOTOPES
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
ISOTOPES
LIGHT NUCLEI
MEASURING INSTRUMENTS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
PULSE CIRCUITS
RADIATION DETECTION
RADIATION DETECTORS
RADIOISOTOPES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
STABLE ISOTOPES
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES
220900* - Nuclear Reactor Technology- Reactor Safety
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)