Published 1980
| Version v1
Report
Open
Multidimensional effects in the thermal response of fuel rod simulators
Description
One of the primary objectives of the Oak Ridge National Laboratory Pressurized-Water Reactor Blowdown Heat Transfer Separate-Effects Program is the determination of the transient surface temperature and surface heat flux of fuel pin simulators (FPSs) from internal thermocouple signals obtained during a loss-of-coolant experiment (LOCE) in the Thermal-Hydraulics Test Facility. This analysis requires the solution of the classical inverse heat conduction problem. The assumptions that allow the governing differential equation to be reduced to one dimension can introduce significant errors in the computed surface heat flux and surface temperature. The degree to which these computed variables are perturbed is addressed and quantified
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
12588165.pdf
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- CONF-801091--5
Conference
- Title
- International symposium on fuel rod simulators-development and application.
- Dates
- 22 - 24 Oct 1980.
- Place
- Gatlinburg, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12588165
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL RODS; HEAT TRANSFER; HEATERS; LOSS OF COOLANT; PERFORMANCE; PWR TYPE REACTORS; REACTOR SAFETY; SIMULATION; SPATIAL DISTRIBUTION; THERMOCOUPLES
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; FUEL ELEMENTS; MEASURING INSTRUMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS