Fast-neutron hodoscope at TREAT: data processing, analysis, and results
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:7138286
The fast-neutron hodoscope at the Transient Reactor Test Facility is designed for the determination of fuel motion during the course of brief (0.1- to 30-sec) power transients. During the course of a transient test, data must be recorded from each of 334 hodoscope channels at count rates up to 2 million/sec each, down to millisecond time intervals. This is accomplished in a relatively reliable and inexpensive manner by displaying counts from each detector sequentially in binary code on a lamp panel, which is photographed by a high-speed framing camera, producing a film record of the transient test. After chemical development, the film is examined by a computer-controlled flying-spot scanner, and the position and density of candidate lamp images are recorded on magnetic tape. Through further computer processing, these images are sorted and decoded, and the count rate is recovered for each detector at each instant of collection time. A cathode-ray tube and a plotter, both computer controlled, are used to recreate and analyze the fuel motion history of the experiment. Analysis is directed toward fuel distortion or expansion prior to clad failure, slumping, dispersion, amount and rates of movement, post-scram relocation, and ultimate disposition of fuel.
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 7138286
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 30:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
TREAT fast-neutron hodoscope: improvements in time and mass resolution of fuel motion
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Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6786663
Maximum-likelihood deconvolution of TREAT hodoscope scan data
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5884226
Fast-Neutron Hodoscope at Treat: Development and Operation
Journal Article
·
Fri Oct 31 23:00:00 EST 1975
· Nucl. Technol., v. 27, no. 3, pp. 449-487
·
OSTI ID:4061424
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
AIR COOLED REACTORS
BARYONS
DATA ACQUISITION SYSTEMS
DESIGN
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FAST NEUTRONS
FERMIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HADRONS
HODOSCOPES
HOMOGENEOUS REACTORS
NEUTRONS
NUCLEONS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
TREAT REACTOR
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
AIR COOLED REACTORS
BARYONS
DATA ACQUISITION SYSTEMS
DESIGN
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FAST NEUTRONS
FERMIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HADRONS
HODOSCOPES
HOMOGENEOUS REACTORS
NEUTRONS
NUCLEONS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
TREAT REACTOR