Nora Dianne Bull Ezell
Profile Information
- Name
- Dr. Nora Dianne Bull Ezell
- Institution
- Oak Ridge National Laboratory
- Position
- R&D Engineer
- h-Index
- ORCID
- 0000-0001-9334-5822
- Biography
- <p>N. Dianne Bull Ezell<b> </b>joined ORNL as R&D Staff member in July 2011 after completing a 9-month post-master’s internship. She completed a Ph.D. in 2016 focusing on signal processing of EMI rejection for Johnson Noise Thermometry measurements in 2016, from the University of Tennessee. Her research interests are system architecture and integration as well as low-power mixed-signal electronic design for nuclear instrumentation. A few of her on-going projects at ORNL are systems engineer for A Large Ion Collider (ALICE) at CERN, technical lead of the non-destructive evaluation (NDE) program, and system engineer of nuclear instrument design for advanced reactors. Dianne recently started developing irradiation experiments in support of the molten salt campaign. She received a BS in Electrical Engineering (2007) and an MS in Electrical Engineering (2009) from the University of Tennessee with research focused on integrated circuit design for hybrid electric vehicles, medical sensors, and lithography.</p><p style="margin-bottom: 0.0001pt; line-height: normal"></p>
- Expertise
- Analog Electronics, Nuclear Instrumentation, System Integration
Publications:
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"In-Rod Sensor System Overview, Benefits and Recent Irradiation Test Results"
Jorge Carvajal, Shawn Stafford, Jeffrey Arndt, Paul Sirianni, Christian Petrie, Nora Dianne Bull Ezell, Daniel Sweeney, Padhraic Mulligan, Austin Shay Chapel,
13th Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2023)
Vol.
2023
8-20
Link
Westinghouse is developing an In-Rod Sensor (IRS) System [1, 2] capable of measuring critical fuel rod parameters such as center-line fuel temperature, rod internal pressure and axial fuel pellet stack elongation without having penetrations to the fuel rod. The technology is similar to the Halden Reactor instrumentation [3], but the IRS system focuses on commercial fuel rod instrumentation. Both systems circumvent fuel rod penetrations, however the IRS system overcomes unique geometric challenges found in commercial fuel rod assemblies. The IRS could also play a key role in accelerated fuel qualification by allowing real-time measurements during separate effects tests, integral fuel testing or during irradiation of lead test rods or lead test assemblies. Combining these measurements with data acquired from targeted separate effects testing and multi-scale modelling could significantly reduce the time required to qualify new fuel and reduce the safety margin uncertainty of operating plants. The IRS is actively in development for Light Water Reactors (LWR) based fuel assemblies but can also be applied to Gen IV reactor designs with minimal modifications. |
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"WIRE-21 Experiment Irradiation Conditions and In-Situ Data Collection"
Christian Petrie, Daniel Sweeney, Padhraic Mulligan, Kara Godsey, Nora Dianne Bull Ezell, Paul Sirianni, Shawn Stafford, Jeffrey Arndt, Jorge Carvajal,
Vol.
2023
Link
This report summarizes the in situ data collected during three cycles of irradiation (~75 days) of the
Wireless Instrumented Removable Beryllium Experiment 2021 (WIRE-21) in the removable beryllium
(RB) positions of the High Flux Isotope Reactor (HFIR). The experiment was designed primarily to
evaluate the effects of high neutron flux and fluence on the performance of wireless temperature and
pressure sensors being developed by Westinghouse Electric Company (WEC). WEC’s sensors could
provide critical data regarding the evolution of centerline temperatures and pressurization due to fission
gas release during fuel operation in light-water reactors (LWRs) or various advanced reactor applications.
In addition to WEC’s wireless sensors, many other sensors were interrogated, including thermocouples,
self-powered neutron detectors (SPNDs), distributed fiber optic temperature sensors, and passive neutron
flux wires and silicon carbide thermometry.
WIRE-21 was irradiated for a total of 75 effective full-power days over five full or partial HFIR cycles,
resulting in maximum thermal and fast neutron fluences of 5.8 × 1021 and 3.4 × 1021 n/cm2, respectively.
Although two exposed thermocouples located inside WEC’s sensors failed during the first irradiation
cycle, the remaining 10 thermocouples that were functional at the start of the irradiation survived for the
entire duration of the experiment. Measured temperatures were within the range of typical LWR operating
conditions: most thermocouples reading in the ~300–400°C range. The four SPNDs all showed a
measurable response to changes in reactor power, but each SPND responded differently. The fiber optic
sensors show interesting evolutions in reflected signal intensities that depend significantly on the fiber
dopants, type of fiber Bragg gratings (FBGs), and the light guiding mechanism (total internal reflection
vs. photonic band gap). The discrepancies in the SPND data and the detailed evolution of the fiber optic
sensors are being investigated by the Advanced Sensors and Instrumentation program of the US
Department of Energy, Office of Nuclear Energy.
Multiple temperature and pressure transients were actuated to compare the response of WEC’s sensors
with reference thermocouples or ex-core pressure transducers, respectively. WEC’s sensors successfully
captured all actuated temperature transients, even after accumulating fast neutron fluence on the order of
2 × 1021 n/cm2. Significant reductions in the inductance in WEC’s six inductors caused some drift in the
wireless sensors. These effects appear to be related to rate effects (i.e., higher neutron flux), as they were
not observed during previous testing at lower neutron flux. However, WEC’s temperature sensor
remained functional even after the inductances decreased. Unfortunately, WEC’s pressure sensor showed
no response during pressurization of the metal bellows. Post-irradiation examination will help inform why
the sensor did not respond to changes in applied pressure and determine the mechanism for the decrease
in inductances. |
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"WIRE-21 Sensor Irradiation Experiment Ready for HFIR Insertion"
Christian Petrie, Austin Shay Chapel, Padhraic Mulligan, David Bryant, Daniel Sweeney, Adam James, Nora Dianne Bull Ezell, Kurt Smith, Kara Godsey, Maureen Searles, Shawn Stafford, Jeffrey Arndt, Jorge Carvajal,
Vol.
2022
Link
The ability to deploy new nuclear fuels for current or future reactor concepts requires a wealth of data regarding fuel performance during normal operation, anticipated operational occurrences, and design-basis accidents. Most of these data have historically been collected during experiments in materials test reactors, ideally with online instrumentation to collect as much data as possible. However, advanced instrumentation could also allow for in situ monitoring of fuel operating conditions during commercial reactor operation to maximize fuel utilization, reduce unnecessary conservativism in design margins, and improve operator understanding of limiting peaking factors. The latter approach would complicate fuel handling, particularly during refueling, unless the instrumentation could be placed inside the fuel rods and transmitted wirelessly to a receiver located outside the fuel’s primary pressure boundary. To this end, Westinghouse Electric Company (WEC) developed wireless sensors based on inductive coupling that can transmit information regarding fuel centerline temperatures and rod internal pressures wirelessly from within a fuel rod to a nearby instrument thimble. After testing these sensors in lower-power university research reactors, the next step is to perform high neutron fluence testing to characterize the performance of these wireless sensors under conditions that are more representative of the intended application—in this case, light-water reactors (LWRs). The removable Be (RB) positions of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) provide the neutron flux, experiment volume, and access to instrument leads required to achieve these sensor testing goals.
This report summarizes the design, analysis, and assembly of the Wireless Instrumented RB Experiment 2021 (WIRE-21). This is the most highly instrumented irradiation experiment ever performed in HFIR. The experiment will use seven different sensing techniques to measure temperature, pressure, neutron flux, and neutron fluence during reactor operation. In addition to WEC’s wireless temperature and pressure sensors, WIRE-21 includes an array of thermocouples, self-powered neutron detectors, spatially distributed fiber optic temperature sensors, passive SiC temperature monitors, and flux wires. The design of WIRE-21 and the cabling that was installed in HFIR also provide the infrastructure to enable accelerated, economical testing of advanced sensor technologies while leveraging the extremely high neutron flux that is available in HFIR. The containment for WIRE-21 is similar to previous RB irradiation vehicles but includes a few modifications, most notably the use of integrated compression seals to pass a larger number of sensor leads through the experiment’s pressure boundary. In addition to the sensor leads, inert gas lines are passed into the experiment to enable active temperature control and the ability to pneumatically actuate a bellows-driven pressure sensor. WIRE-21 is targeting component temperatures (300–350°C) and neutron fluence levels (~1022 n/cm2) that would be expected in the plenum region of LWR fuels, except for the active sensing region of the wireless temperature sensor, which is targeting LWR fuel centerline temperatures (~800–1,100°C). WIRE-21 was successfully assembled, passed all nondestructive examination, and was delivered to HFIR for insertion during upcoming cycle 498 (April 2022). |
Accomplishments
NSUF Supported Research
NSUF Research Collaborations
Neutron Irradiation and PIE of ZrC Coated Surrogate Particle Fuel in IN-Pile Steadystate Extreme Temperature (INSET) Testbed - FY 2024 Super RTE Call, #24-5070
Irradiation of GaN HEMTs and SiC JFETs for Near Core Rad-hard Electronics - FY 2024 RTE 1st Call, #24-4881
Irradiation of Radiation-hard GaN Transistors for Mixed Gamma and Neutron Field Under High Temperature - FY 2023 RTE 1st Call, #23-4530
Neutron Irradiation of a radiation resistant digitizer at PULSTAR - FY 2023 RTE 1st Call, #23-4606
Neutron Irradiation of Updated In-Pile Steady State, Extreme Temperature Experiment (INSET) - FY 2023 RTE 1st Call, #23-4603