Data report for the NRC/PNL Halden assembly IFA-431.
The report presents the in-reactor data collected from the NRC/PNL Halden Assembly IFA-431 as a part of the program entitled ''Experimental Verification of Steady State Fuel Codes,'' sponsored by the Fuel Behavior Research Branch of the USNRC. The purpose of this program is to reduce the uncertainties of calculating the thermal stored energy in an operating nuclear fuel rod. The report presents fuel centerline thermocouple readings, cladding elongation monitor readings, rod internal pressure readings, and neutron detector readings. The neutron detector readings were corrected to represent rod local powers at the thermocouple locations. These data are presented in the form of plots of the variables versus time during the irradiation period from June 1975 to February 1976. Also included are descriptions of the test rationale, assembly and rod designs, test facility, instrument array and calibration, and data processing methods. Topical reports discussing specific aspects and results of the data analysis are referenced.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 6718024
- Report Number(s):
- PNL-2494
- Country of Publication:
- United States
- Language:
- English
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HEAVY WATER COOLED REACTORS
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LOSS OF COOLANT
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PWR TYPE REACTORS
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