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Response of the SPND measurement system to temperature during the Three Mile Island Unit 2 accident. [Self-Powered Neutron Detector]

Authors: Wilde, N.; Morrison, J.L. Jr.;

Response of the SPND measurement system to temperature during the Three Mile Island Unit 2 accident. [Self-Powered Neutron Detector]

Abstract

The Self-Powered Neutron Detector (SPND) Measuring System is evaluated to determine its ability to indicate temperatures of the fuel rods in the TMI-2 reactor core during the accident. It is concluded for the following reasons that the SPND Measuring System did not provide fuel rod temperatures during the accident: the heat transfer characteristics vary over a range of five octaves; within the range of 1200 to 1800/sup 0/F, the SPND responds to temperature from convection radiation from the fuel rods and self-heating from the gamma flux; within the range of 1200 to 1800/sup 0/F, the signal cable introduces masking signals that are a function of gamma heating, integrated temperature over the cable, and core water level velocity; the data system's worst-case signal-to-noise ratio from aliasing is 0dB; and the recorder system's worst-case signal-to-noise ratio from aliasing is -24dB.

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United States
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Keywords

Enriched Uranium Reactors, Signals, 440101 -- Radiation Instrumentation-- General Detectors Or Monitors & Radiometric Instruments, Performance, Nonbreeding, Nonboiling Water Cooled, Equipment, 21 Specific Nuclear Reactors And Associated Plants, Reactor Accidents, Cables, Fuel Rods, Heating, Radiations, 46 Instrumentation Related To Nuclear Science And Technology, Conductor Devices, Fuel Elements, Reactor Components, Light-Water Moderated, Electrical Equipment, 22 General Studies Of Nuclear Reactors, Gamma Radiation, Radiation Heating, Electromagnetic Radiation, Temperature Measurement, Pwr Type Reactors, Thermal Reactors, Reactors, Measuring Instruments, Neutron Detectors, Three Mile Island-2 Reactor, Power Reactors, Accidents, Electric Cables, Radiation Detectors, 210200 -- Power Reactors, Water Cooled Reactors, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Ionizing Radiations

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selected citations
These citations are derived from selected sources.
This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Citations provided by BIP!
popularity
This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.
BIP!Popularity provided by BIP!
influence
This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Influence provided by BIP!
impulse
This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.
BIP!Impulse provided by BIP!
0
Average
Average
Average
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