The Oregon State TRIGA Reactor (OSTR) is a
TRIGA Mk. II research reactor, developed by
General Atomics, with a maximum licensed thermal output of 1.1 MW, and it can be pulsed up to a power of 3000 MW for a very short time. The fuel is high-assay, low-enriched uranium (
HALEU) in the form of
uranium zirconium hydride (UZrH) with an erbium
burnable poison. Operation began in 1967. The reactor supported 96 academic courses in 1999. These courses were in
chemistry,
civil engineering,
chemical engineering,
geosciences,
oceanography and
atmospheric sciences,
bioresource engineering, honors college and
naval engineering disciplines. The OSU Radiation center supported 126 projects in 2000 with 69% directly involving use of the OSTR. Contracts supporting these projects in 2000 totaled $3 million.
In-Core Irradiation Facilities The OSTR has six in-core irradiation facilities. The Central Thimble is a water-filled tube extending down into the reactor core central grid position A-1. Its purpose is to provide the highest flux possible; however, it is currently not in use at OSTR due to numerous practical and experimental constraints. The
Cadmium-Lined In-Core Irradiation Tube (or CLICIT) is an air-filled aluminum tube surrounded by a thin lining of cadmium metal that occupies the B-1 grid position in the central area of the core. Cadmium is a
thermal neutron absorber, allowing only
epithermal neutrons and
fast neutrons to enter. The primary purpose of this facility is
Ar-Ar dating,
K-Ar dating, and
neutron activation analysis via
neutron bombardment. The In-Core Irradiation Tube (or ICIT) is located in grid position F-12 in the second-most outer ring of the reactor core, and it provides the highest
neutron flux of any facility currently in use at OSTR. It is identical in construction to the CLICIT but lacks cadmium lining, resulting in unfiltered neutron irradiation. The
Cadmium-Lined Outer-Core Irradiation Tube (or CLOCIT) is identical in construction to the CLICIT and is positioned in the same ring as the ICIT, in grid position F-20. Its purpose is identical to the CLICIT; however, due to its location in the core periphery and the neutron flux profile in the core, irradiations take 1.8 times longer to provide the same
neutron fluence as an irradiation in the B1 CLICIT. The
Pneumatic Transfer System, colloquially known as the , is an irradiation facility that is pneumatically operated to rapidly insert and remove samples from the outermost ring of the core in position G-2. Irradiations can be performed for as little as five seconds and samples are prepared, sent, and received from a fume hood in an auxiliary laboratory adjacent to the reactor bay. The primary purpose of this facility is to perform
neutron activation analysis using isotopes with short
half-lives. The Rotating Rack, colloquially known as the
Lazy Susan, is a ring-shaped container surrounding the core between the core and the graphite
neutron reflector. It rotates around the core about once a minute, providing an even flux to the samples inside. This facility has 40 nitrogen-filled slots for samples to be irradiated in.
Thermal column The thermal column is a large
graphite slab that pierces the concrete bioshield of the reactor and makes contact with the
graphite neutron reflector surrounding the core. The purpose of the thermal column is to create an irradiation facility that filters out high energy neutrons to create a high
thermal neutron flux. The thermal column is primarily used for fission tracking of certain minerals that contain
fissile material.
Neutron Beam Ports The OSTR has four neutron beam ports that penetrate the reactor tank and allow intense neutron and gamma radiation to exit the concrete bioshield for various research and commercial purposes. Of the four beam ports at OSTR, there are two radial beam ports, one tangential beam port, and one radial piercing beam port. All three radial beam ports are aligned with the axial midplane of the reactor core, and point directly at the center of the core. The two, standard radial beam ports (beam ports #1 and #2) terminate at the outer radius of the graphite neutron reflector, but are aligned with air-filled cans within the reflector to limit neutron scattering and absorption in the beam lines. The radial piercing beam port (beam port #4) terminates at the inner radius of the graphite neutron reflector annulus, and is connected to the reflector via a bellows to accommodate thermal expansion differences between the reactor tank and reactor core assembly. The tangential beam port (beam port #3) runs tangent to the reactor core and terminates at the outer radius of the graphite neutron reflector. Like the standard radial ports, an air-filled can is within the reflector and aligned with the beam port, adjacent to beam port #4, the piercing beam port. As of now, there are only two beam ports in use at OSTR: beam port #1 and beam port #3. Beam port #3, the tangential beam port, is the most used beam port at the OSTR. The facility attached is used for
neutron radiography and, as such, is called the Neutron Radiography Facility or NRF. The NRF houses an pneumatically-controlled, counter-balanced beam shutter made of boral (a boron-aluminum composite material) and lead, that allows the operator to control the facility from outside the facility. The facility features numerous safety mechanisms to ensure the access doors and shutter are never open in conjunction, including an automatic reactor scram system if the shutter and doors are open together. Beam port #1, one of the standard, radial ports, is used for many research purposes. The facility attached currently is called the Beam Port #1 Facility (BP1F), and is a repurposed version of the Prompt Gamma Neutron Activation Analysis (PGNAA) facility that was once installed on Beam Port #4, before it was decommissioned due to a small reactor tank leak. The BP1F can perform
prompt gamma neutron activation analysis, as well as low-magnitude neutron flux irradiations. ==Safety==