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Lambson, Ashley A.

Publications and source records attributed to Lambson, Ashley A..

Laboratory and In-Pile Testing of a Fiber Optic Pressure Sensor

The development, testing and deployment of a fiber-optic-based extrinsic Fabry-Perot pressure sensor is discussed. The details of design and fabrication procedure is discussed and the methodology for design decisions is provided. Results from laboratory-based testing and calibration is provided as-well-as preliminary data from in-pile testing in the Transient Reactor Test Facility.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Evaluation of Low Dose Silicon Carbide Temperature Monitors

Thermocouples are generally used to provide real-time temperature indications in instrumented tests performed at materials and test reactors. Melt wires or paint spots are often included in such tests as an independent technique of detecting peak temperatures incurred during irradiation. In addition, less expensive static capsule tests, which have no leads attached for real-time data transmission, often rely on melt wires and paint spots as a post-irradiation technique for peak temperature indication. Unfortunately, these techniques are limited in that they can only detect whether a single temperature is or is not exceeded. Silicon carbide (SiC) monitors are advantageous because a single monitor can be used to determine the peak temperature reached within a relatively broad range (200 – 800°C). Although the use of SiC monitors was proposed more than five decades ago, the ultimate performance limits of this technique are not fully understood. The Nuclear Science User Facilities (NSUF) is the United States Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Its mission is to provide nuclear energy researchers access to world-class capabilities and to facilitate the advancement of nuclear science and technology. This mission is supported by providing access to state-of-the-art experimental irradiation testing, post irradiation examination facilities, and high performance computing capabilities as well as technical and scientific assistance for the design and execution of projects. As part of an NSUF project, low dose silicon carbide monitors were irradiated in the Belgian Reactor 2 and were then evaluated both at the SCK•CEN and at Idaho National Laboratory's High Temperature Test Laboratory to determine their peak temperature achieved during irradiation. The technical significance of this work was that the monitors were irradiated to a dose that was significantly less than recommended in published literature. This paper will discuss the evaluation process, the irradiation test, and the performance of the low dose silicon carbide temperature monitors.

36 MATERIALS SCIENCE↗

Recovery of Silicon Carbide monitor irradiation temperature via continuous resistance measurement during annealing (Pt. II)

Silicon carbide (SiC) monitors provide a means of measuring peak irradiation temperature of experiment capsules in nuclear irradiation experiments. Neutron irradiation of a SiC monitor causes permanent lattice changes that are removed by annealing via heating to a temperature that exceeds the peak irradiation temperature. The annealing process results in changes to SiC physical characteristics that can be observed during the annealing process. This paper presents results of a method aimed at using electrical resistance, measured during a two-pass heating – cooling cycle as a means of recovering the irradiation temperature of a SiC monitor. Results indicate that the relationship between resistance and temperature of a SiC monitor shows a significant change in slope when the peak irradiation temperature is reached. This demonstrates the potential for this method to replace the current manual, and lengthy, process of post irradiation examination used to extract the peak irradiation temperature from irradiated SiC monitors.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

FY19 Report for Instrumentation Development for the Transient Testing Program

This report details the technical activities and accomplishment carried out under funding from the Department of Energy (DOE) Nuclear Technology Research and Development (NTRD) program for in-pile instrumentation supporting the transient testing program in FY19. These activities were performed in support of cross-cutting transient testing experiment objectives. The purpose of this report is to provide a summary of key technical work, of particular interest to nuclear irradiation test experimenters and in-pile instrumentation engineers. During FY19, development activities are focused on deployment of devices to perform online measurement of neutron flux, temperature, and mechanical behaviors in nuclear fuels experiments. Specifically, these R&D activities include in-pile investigations at the Transient Reactor Test (TREAT) facility throughout the year. Other in-pile instrumentation R&D activities are being carried out under other DOE programs, which may be recognized but not the focus of this document. A brief summary of activities and accomplishments is first provided for each major activity. More detailed summaries are presented in appendices.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗