Published 1979
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LOFT two-phase flow data integrity analysis
Description
Data integrity methods have been developed and applied to Loss-Of-Fluid Test (LOFT) nuclear reactor safety experiments at the Idaho National Engineering Laboratory. The methods for imroving and qualifying the accuracy of transient measurements on complex thermal-hydraulic experiments are described. These methods involve use of all the information available on the transducers, including data taken during the LOFT experiment itself. Optimum use of these methods determine, in part, the instrumentation package provided on the experiment
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
10480065.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 3 p.
- Report number
- CONF-790505--8
Conference
- Title
- 25. ISA international instrumentation symposium.
- Dates
- 7 - 9 May 1979.
- Place
- Anaheim, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10480065
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LOFT REACTOR; LOSS OF COOLANT; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS