A Portable Measurement System for Subcriticality Measurements by the CF-Source-Driven Neutron Noise Analysis Method
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Instrumentation and Controls Division
A portable system has been assembled that is capable of measuring the subcriticality of fissile materials using the 252CF-source-driven neutron noise analysis method. The measurement system consists of a parallel-plate ionization chamber containing 252CF, two 3He proportional counters with their associated electronics, and a small computer containing anti-aliasing filters and A/D convertors. The system Fourier analyzes the digitized data and forms the appropriate auto and cross-power spectral densities. These spectra are used to form a ratio of spectral densities, G12 G13/G11 G23, where 1 refers to the ionization chamber, and 2 and 3 refer to the /sup 3/He counters, from which subcriticality can be determined. The chamber and detectors are located appropriately near the fissile material. The system is capable of sampling signals at rates of up to 80 kHz and processing these data at rates of 2 kHz to form the appropriate spectra. The presently configured system is a two-channel system, hence the measurement of G12, G13, and G23 must be done sequentially before the ratio of spectral densities is obtained. Future improvements of the system will allow simultaneous measurement of all spectra and will further reduce size, thereby enhancing portability. This measurement system can provide reliable, cost effective, and convenient determination of the subcriticality of a wide variety of fissile materials and moderators.
- 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)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6219178
- Report Number(s):
- CONF-871005-1; ON: DE87008592; TRN: 87-032171
- Resource Relation:
- Journal Volume: 35; Journal Issue: 1; Conference: IEEE Nuclear Power Systems Symposium, San Francisco, CA (United States), 21-23 Oct 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Determination of Reactivity from Power Spectral Density Measurements with Californium-252
|
journal | April 1978 |
Cf-source-driven neutron-noise measurements of subcriticality for a 4.95 wt% 235U-enriched uranyl fluoride solution cylinder
|
journal | January 1986 |
Subcriticality Measurements for Coupled Uranium Metal Cylinders Using the252Cf-Source-Driven Neutron Noise Analysis Method
|
journal | January 1987 |
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
FISSILE MATERIALS
NEUTRON SPECTROSCOPY
SUBCRITICALITY
PORTABLE EQUIPMENT
CALIFORNIUM 252
IONIZATION CHAMBERS
MODERATORS
NEUTRONS
NOISE
PROPORTIONAL COUNTERS
SPECTRAL DENSITY
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
CALIFORNIUM ISOTOPES
ELEMENTARY PARTICLES
EQUIPMENT
EVEN-EVEN NUCLEI
FERMIONS
FISSIONABLE MATERIALS
FUNCTIONS
HADRONS
HEAVY NUCLEI
ISOTOPES
MATERIALS
MEASURING INSTRUMENTS
NUCLEI
NUCLEONS
RADIATION DETECTORS
RADIOISOTOPES
SPECTRAL FUNCTIONS
SPECTROSCOPY
YEARS LIVING RADIOISOTOPES
Nuclear Criticality Safety Program (NCSP)
Cross-Power Spectral Density (CPSD)
Auto-Power Spectral Density (APSD)
Fissile System
Fourier Analyzer
Analog-to-Digital (A/D)
Neutron Multiplication Factor
440103* - Radiation Instrumentation- Nuclear Spectroscopic Instrumentation