Jump to content

UHTREX

From Wikipedia, the free encyclopedia

TheUltra-High Temperature Reactor Experiment(UHTREX) was an experimentalgas-coolednuclear reactor run at Los Alamos National Laboratory between 1959 and 1971[1][2]as part of research into reducing the cost of nuclear power.[3]Its purpose was to test and compare the advantages of using a simple fuel against the disadvantages of a contaminatedcooling loop.[4]It first achieved full power in 1969.[5]

The experiment was a spin-off fromProject Rover,intended to develop anuclear thermal rocket.[1]

Reactor core design[edit]

The UHTREX core was composed of a vertical hollow rotating cylinder (turret) constructed of solidgraphite.

UHTREX Reactor Core Vertical Cross Section 1
The pure graphite neutron moderator of the Ultra-high temperature reactor experiment (UHTREX)

Thecylinderwas 70 in. OD x 23 in. ID x 39 in. high. The core had 312 fuel channels. The channels were equally spaced radially around the core at 15 degree intervals arranged in 13 separate layers of 24 channels each. Each channel held up to 4 fuel elements and extended completely through to the inside of the cylinder. The core could be refueled remotely while at full power.[4]Refueling involved rotating the core to the channel containing the element requiring replacement and pushing in a new element. The used element would be pushed out into the center and fall to the base of the reactor to be collected. At full power the reactor used up 1 to 6 fuel elements per day depending on enrichment and porosity of the fuel element. It produced 3MW of thermal energy.

Advantages[edit]

A typicalnuclear reactorprevents the coolant medium from directly contacting the fuel pellets either by cladding the fuel pellets, sealing the fuel pellets inside afuel rodor running the coolant through separate piping. This prevents contamination of the cooling medium. One of the disadvantages of a sealed fuel assembly includes buildup offission productsinside the fuel element. Some of these productspoisonthe reaction ultimately leading to poor efficiency well before a significant portion of the fuel is used up. At this time the reactor requires re-fueling. Keeping the fuel and coolant separate can present significant design challenges as well. For example, the metal tubing required to do so cannot be operated at temperatures above its melting point which is generally significantly lower than the fuel pellet. This lowers the maximum theoreticalthermal efficiencyof the reactor.

The UHTREX used un-clad porous carbon extruded fuel elements each shaped like a long hollow cylinder.[4]The fuel elements were manufactured by vacuum impregnating the porous carbon cylinders with aqueousuranyl nitratesolution then air drying and baking them in a furnace ultimately producing auranium oxidecoating tightly held in a porous graphite matrix.[4]This fuel was expected to be substantially less expensive to manufacture[4]than other types of fuel at the time. The primary advantages of this type of fuel was that the porosity of the pellet in addition to the high temperatures achievable would allow most of the poisons created by thefission productsto migrate out of the fuel. The poisons would then be carried away by the coolant stream for eventual filtering out and removal. This allows a higher percentage of fuel to be burned up before the pellet needed replacement (up to 50%).[4]

Disadvantages[edit]

The major disadvantage to porous reactor fuel is that the entire primary cooling loop including all thepumps,compressorsandheat exchangerswould become highly contaminated withfission products.[4]Contamination caused by a potential contaminatedcoolantleak would pose a significant danger to personnel and the environment. The high contamination level precludes being able to open the reactor vessel for the eventual refueling. Therefore, the reactor was designed for remoteonline refuelling.

Specifications[edit]

UHTREX had following specifications:[4]

  • Fuel -highly enriched uranium
  • Rated power - 3 MW (thermal)
  • Core construction material - graphite
  • Moderator - graphite
  • Reactor vessel -carbon steelsphere 13 ft. 2 in. diameter 1.75 inches thickness.
  • Fuel channels - 312 channels. Each one is 1.1 in. ID, 23.5 in. long and holds up to 4 fuel elements.
  • Fuel element - 1 in. OD, 0.5 in. ID and 5.5 in. long (25.4 mm x 12.7 mm x 139.7 mm).
  • Core power density - 1.3 W/cc
  • Fuel utilization - up to 50%.
  • Coolant -heliumat 500psi(3.45 MPa)
  • Coolant temperature - inlet 1600 °F, Outlet 2400 °F (871 °C and 1316 °C).
  • Coolant flow rate - 10,250 pounds per hour (1.294 kg/s)

where ID and OD are the inner and outer diameter, respectively.

See also[edit]

References[edit]

  1. ^abThe Bradbury YearsfromLos Alamos ScienceWinter/Spring 1983 (Los Alamos National Laboratory).
  2. ^The Agnew YearsfromLos Alamos ScienceWinter/Spring 1983 (Los Alamos Scientific Laboratory).
  3. ^The AtomVolume 11 #51 (Jan-Feb 1974)
  4. ^abcdefghULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT,Los Alamos Science Document #LA-2689 (1962).
  5. ^Milestones in the history of Los Alamos National Laboratory,Los Alamos Science Document Number 21-1993.
Retrieved from "https://en.wikipedia.org/w/index.php?title=UHTREX&oldid=1196147098"