Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments
Abstract
Data from the Loss-of-Fluid Test (LOFT) Program help quantify the margin of safety inherent in pressurized water reactors during postulated loss-of-coolant accidents (LOCAs). As early as 1979, questions arose concerning the accuracy of LOFT fuel rod cladding temperature data during several large-break LOCA experiments. This report analyzes how well externally-mounted fuel rod cladding thermocouples in LOFT accurately reflected actual cladding surface temperature during large-break LOCA experiments. In particular, the validity of the apparent core-wide fuel rod cladding quench exhibited during blowdown in LOFT Experiments L2-2 and L2-3 is studied. Also addressed is the question of whether the externally-mounted thermocouples might have influenced cladding temperature. The analysis makes use of data and information from several sources, including later, similar LOFT Experiments in which fuel centerline temperature measurements were made, experiments in other facilities, and results from a detailed FRAP-T6 model of the LOFT fuel rod. The analysis shows that there can be a significant difference (referred to as bias) between the surface-mounted thermocouple reading and the actual cladding temperature, and that the magnitude of this bias depends on the rate of heat transfer between the fuel rod cladding and coolant. The results of the analysis demonstrate clearly that a core-wide claddingmore »
- Authors:
-
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Org.:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI Identifier:
- 10165497
- Report Number(s):
- NUREG/CR-6061; EGG-2610
ON: TI93014900; TRN: 93:015327
- DOE Contract Number:
- AC07-76ID01570
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: PBD: May 1993
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; LOSS OF COOLANT; FUEL CANS; TEMPERATURE MEASUREMENT; THERMOCOUPLES; ACCURACY; LOFT REACTOR; BLOWDOWN; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; FUEL RODS; DATA ANALYSIS; TEST FACILITIES; 220900; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
Citation Formats
Berta, V T, Hanson, R G, Johnsen, G W, and Schultz, R R. Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments. United States: N. p., 1993.
Web. doi:10.2172/10165497.
Berta, V T, Hanson, R G, Johnsen, G W, & Schultz, R R. Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments. United States. https://doi.org/10.2172/10165497
Berta, V T, Hanson, R G, Johnsen, G W, and Schultz, R R. 1993.
"Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments". United States. https://doi.org/10.2172/10165497. https://www.osti.gov/servlets/purl/10165497.
@article{osti_10165497,
title = {Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments},
author = {Berta, V T and Hanson, R G and Johnsen, G W and Schultz, R R},
abstractNote = {Data from the Loss-of-Fluid Test (LOFT) Program help quantify the margin of safety inherent in pressurized water reactors during postulated loss-of-coolant accidents (LOCAs). As early as 1979, questions arose concerning the accuracy of LOFT fuel rod cladding temperature data during several large-break LOCA experiments. This report analyzes how well externally-mounted fuel rod cladding thermocouples in LOFT accurately reflected actual cladding surface temperature during large-break LOCA experiments. In particular, the validity of the apparent core-wide fuel rod cladding quench exhibited during blowdown in LOFT Experiments L2-2 and L2-3 is studied. Also addressed is the question of whether the externally-mounted thermocouples might have influenced cladding temperature. The analysis makes use of data and information from several sources, including later, similar LOFT Experiments in which fuel centerline temperature measurements were made, experiments in other facilities, and results from a detailed FRAP-T6 model of the LOFT fuel rod. The analysis shows that there can be a significant difference (referred to as bias) between the surface-mounted thermocouple reading and the actual cladding temperature, and that the magnitude of this bias depends on the rate of heat transfer between the fuel rod cladding and coolant. The results of the analysis demonstrate clearly that a core-wide cladding quench did occur in Experiments L2-2 and L2-3. Further, it is shown that, in terms of peak cladding temperature recording during LOFT large-break LOCA experiments, the mean bias is 11.4 {plus_minus} 16.2K (20.5 {plus_minus} 29.2{degrees} F). The best-estimate value of peak cladding temperature for LOFT LP-02-6 is 1,104.8 K. The best-estimate peak cladding temperature for LOFT LP-LB-1 is 1284.0 K.},
doi = {10.2172/10165497},
url = {https://www.osti.gov/biblio/10165497},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat May 01 00:00:00 EDT 1993},
month = {Sat May 01 00:00:00 EDT 1993}
}