This work presents a design study on the utilization of Po-210 as an alternative to Pu-238, for the fueling of radioisotope thermoelectric generators (RTGs), particularly destined for short-lived low-earth orbit (LEO) satellite missions. This alpha-emitter based battery  design explores mission critical factors such as the radioisotope required mass, heat-to-electrical energy conversion system and theoretical battery form factors. Three distinct satellite missions are examined to represent the broad scope of power ranges employed by LEO satellites. Based on results for Beginning-of-life (BOL) and End-of-life (EOL) power requirements, a performance envelope is identified for the generic use of 210-Po on RTG-based missions.

The Transient Reactor Test (TREAT) facility is able to test the performance of nuclear fuels and materials under power excursions. Very-brief power bursts meant to simulate postulated Reactivity-Initiated Accidents (RIA) in light water reactors are of keen interest to DOE and industry for the development of advanced nuclear fuels. TREAT is innately capable of performing RIA-type pulse transient excursions. However, the duration (or width) of these excursions is longer than desired for better simulation of RIAs. With some modification, it should be possible to shorten the TREAT pulse-width, thereby allowing investigation of RIAs. To shorten the TREAT pulse-width, it is proposed that a He-3 injection device be integrated into TREAT to clip the pulse. This system has been termed the Helium-3 Enhanced Negative Reactivity Insertion (HENRI) system. Currently, the Full-Width at Half Maximum (FWHM) duration of a TREAT pulse is no shorter than 72 ms. To achieve a desired pulse width in the range of ~40-50 ms, there is a need to rapidly inject He-3 into chambers in the TREAT core.

The project involved the design, construction and testing of an out-of- pile prototype gas injection system (assumedly using conventional helium 4 He), comparison of the empirical results with necessary refinements to the predictive model, and publication of the results.

The hydrodynamics that take place within tandem plate geometry have been linked to failure modes for many diverse applications. Of particular interest is the recent nuclear fuel qualification activities taking place at the Advanced Test Reactor (ATR) at Idaho National Lab (INL). This new fuel plate qualification activities lead to the AFIP-6 Mk II experiment. During AFIP-6 Mk II rectangular fuel plates in tandem orientation were placed inside a flow field which resulted in a trailing plate entirely breaking off and therefore, compromising the design. Vortex induced vibrations were linked to the failure mode experienced by the plate but it is unknown to what extent does the tandem geometry of the plates is directly responsible for altering the frequency of the vortex shedding.  Theoretical solutions for characterizing the vortex shedding frequency only exist for tandem cylinders and single plates but not for plates in a tandem orientation. 

The motivation behind this work is to provide a basis for confidently modeling the flow characteristics of rectangular plates in tandem arrangement, through the use of a CFD tool. This is relevant in order to expand upon the limited experimental data available and developed to directly study the conditions of the flow as it originates the VIV phenomena.

 The Integrated Pump Control Vehicle (IPCV) project involved design, fabrication and testing efforts towards a unique utility cart that can provide ease of transportation and mobility for multi-size naval pumps.

The IPCV falls under the Naval Research Testing Loop (NRTL) project, lead by Principal Investigator Dr. G. Mignot. The project consist on the testing of new pumps intended to be used in the Advanced Test Reactor (ATR) at Idaho National Laboratory. The Advanced Test Reactor (ATR) has provided the critical testing capability that has helped develop the U.S. Navy's nuclear propulsion program & the Navy remains a key customer and user of ATR, according to the Idaho National Laboratory (INL) website.

To support ongoing naval research, the ATR at INL is scheduled to replace the current pumps which have run for more than 45 years.  These new pumps must first be commissioned and rigorously tested. That’s where the NRTL facility at Oregon State comes in and thus the necessity for the IPCV to be developed.

Nuclear Reactor Test Loop (NRTL) facility (http://ne.oregonstate.edu/guillaume-mignot-joins-nse-research-faculty)

The Hydro-Mechanical Fuel Test Facility (HMFTF) is a large-scale thermal-hydraulic separate effects test facility located in the Advanced Nuclear Systems Engineering Laboratory (ANSEL) at OSU. The facility operates under an NQA-1 compliant quality assurance program and is currently listed on the Idaho National Laboratory Quality Supplier List as a level 1 supplier. The facility is designed such that any element which can fit within the inner vertical height of the test section region may be tested. 

The HMFTF was designed to cover the operating envelope of all high performance research reactors in the US while operating under subcooled conditions. The primary loop is rated to 600 psig and 460°F and has the capability to operate with net flow rates ranging from 100 gpm to 1600 gpm. Operators are able to maintain conditions within ± 5 °F, psig, and gpm during testing. In order to recreate the thermal-hydraulic conditions in reactors, the loop can be configured for up or down-flow through the test section

The Athena security system consists of the first ever RFID-based device that is placed directly in the radioisotope source. It features a long battery life and provides real-time tracking and monitoring data 24/7. 

-Athena is meant to serve non-nuclear industries that require the use of sealed isotopes in order to conduct business (Non-destructive radiography, chemical companies, hazardous material disposal, etc.)

- Our technology can continuously monitor and tracked radiation source throughout transportation, storage, processing and disposal.

- Additionally, our services streamlines information management and inventory control to both government authorities and private companies

SEAL stands for Secluded Energy Access to Low-power and it represents an ideal solution to the need for accessing DC power in the event of a Station Blackout (SBO) scenario similar to the one presented at the Fukushima-Daichi plant.

This system features high power density batteries (nearly 3 times power density as current Lead-type batteries) to be placed inside a container underwater and anchored to the sea floor. These units are kept charged and under emergency situations they are called upon to provide the basic functionalities to keep the plant in a safe operating state. The string of batteries feed electricity to the charger which converts the DC power into AC power and feeds to the control panels in the reactor. These batteries are charged from the AC power of the generator (480 Volts AC). Under normal operations these batteries are responsible for providing power for the time between loss of AC power and the time diesel generators kick into full power. Under accident scenarios (Station Blackout) these batteries are intended to provide power between 4-8 hours to perform basic safety related operations. The backup DC battery system can enable an extended loss of all AC coping time of 72 hours for core and spent fuel pool cooling as well as control room integrity as needed.

The SEAL container is equipped with battery panels (shown in grey), power inverters, chargers and monitoring equipment. The most paramount characteristic of the SEAL system, is its location within the power plant space.  By designing the SEAL container to be installed under the sea level and securing it to the sea floor the potential for second modes of failure caused by the natural disaster, gets slightly reduced. The SEAL system takes advantage of the misfortunate characteristic of certain power plants to be located within close proximity to a large body of water (ocean, river, lake).