Published August 1980 | Version v1
Journal article Metadata-only

Use of fuel thermocouple transient response for data verification and fuel rod modeling

Creators

  • 1. Battelle, Pac Northwest Lab, Richland, Wash

Description

Various interacting mechanical and thermal processes operate in a fuel rod during irradiation. Fuel rod modeling codes are written to predict the outcome of these interactions. These two questions concern the statistical confidence limits on thermocouple data for fuel temperature, and an evaluation concerning comparison of data and code prediction. 7 refs

Additional details

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
50
Journal Issue
1
Series
Nucl. Technol.
Journal Page Range
95-107
ISSN
0029-5450

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14724899
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
FUEL RODS; HBWR REACTOR; HEAT TRANSFER; IRRADIATION; TEMPERATURE MEASUREMENT; THERMOCOUPLES; TRANSIENTS
Descriptors DEC
BHWR TYPE REACTORS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MEASURING INSTRUMENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; THERMAL REACTORS