Contact profilometry digital data acquisition and conversion
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6959354
- Brigham Young Univ., Provo, UT (United States)
- Argonne National Lab., IL (United States)
- Argonne National Lab., Idaho Falls, ID (United States)
For many years, the element contact profilometer in the Hot Fuel Examination Facility (HFEF) at Argonne National Laboratory in Idaho has served an important role in the post-irradiation examination of experimental and driver fuel elements irradiated in the Experimental Breeder Reactor II or the Fast Fuel Test Facility. It remotely measures the diameter over the length of irradiated elements. Using these data, an experimenter can determine how the physical shape of an element has changed due to in-reactor exposure. Previously, diameter measurements were mechanically registered on strip charts. Such data required manual entry into computers for subsequent quantitative analysis. Hand entry was time-consuming, occasionally introduced typographical errors, and necessitated subjective interpretation ([open quotes]eye-balling[close quotes]) of diameter strip charts. Storing information on irregularly sized strip charts made archiving difficult. Furthermore, if the element was rotated during measurement, as is necessary for elements with spacer wires, the azimuthal angle could not be recorded. Clearly, experimenters desired a way to eliminate these problems.
- OSTI ID:
- 6959354
- Report Number(s):
- CONF-931160--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
BREEDER REACTORS
DATA ACQUISITION
DIGITAL SYSTEMS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
POST-IRRADIATION EXAMINATION
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SHAPE
SODIUM COOLED REACTORS
TEST REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
BREEDER REACTORS
DATA ACQUISITION
DIGITAL SYSTEMS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
POST-IRRADIATION EXAMINATION
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SHAPE
SODIUM COOLED REACTORS
TEST REACTORS