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The High Flux Isotope Reactor (HFIR) is a nuclear research reactor at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, United States.Operating at 85 MW, HFIR is one of the highest flux reactor-based sources of neutrons for condensed matter physics research in the United States, and it has one of the highest steady-state neutron fluxes of any research reactor in the world.
ORNL has several of the world's top supercomputers, including Frontier, ranked by the TOP500 as the world's second most powerful. The lab is a leading neutron and nuclear power research facility that includes the Spallation Neutron Source, the High Flux Isotope Reactor, and the Center for Nanophase Materials Sciences.
The protons pass into a ring-shaped structure, a proton accumulator ring, where they spin around at very high speeds and accumulate in "bunches." Each bunch of protons is released from the ring as a pulse, at a rate of 60 times per second (60 hertz). The high-energy proton pulses strike a target of liquid mercury, where spallation occurs.
The High Flux Isotope Reactor (HFIR) @ ORNL [41] 100/202 The Spallation Neutron Source (SNS) @ ORNL [42] 450/483 Fusion Energy Sciences (FES) [43] Fusion Facilities The DIII-D (tokamak) National Fusion Facility @ General Atomics [44] NA/429 National Spherical Torus Experiment (NSTX) @ PPPL [45] 300/358 High Energy Physics (HEP) [46]
A nuclear reactor coolant is a coolant in a nuclear reactor used to remove heat from the nuclear reactor core and transfer it to electrical generators and the environment. Frequently, a chain of two coolant loops are used because the primary coolant loop takes on short-term radioactivity from the reactor.
A High Flux Reactor is a type of nuclear research reactor. High Flux Isotope Reactor (HFIR), in Oak Ridge, Tennessee, United States of America, High Flux Australian Reactor (HIFAR), Australia's first nuclear reactor, High-Flux Advanced Neutron Application Reactor (HANARO), in South Korea. The High Flux Reactor at Institut Laue–Langevin in France.
Aiming at a compact core with high power density (i.e. with a high neutron flux) to be able to operate as a materials testing reactor, the fuel to be used in the ADS MYRRHA must be highly enriched in a fissile isotope. A highly enriched MOx fuel with 30 – 35 wt. % of 239 Pu was first selected to obtain the desired neutronic performances.
According to the patent application [5] the reactor design has some notable characteristics, that sets it apart from other reactor designs. It uses uranium hydride (UH 3) "low-enriched" to 5% uranium-235—the remainder is uranium-238—as the nuclear fuel, rather than the usual metallic uranium or uranium dioxide that composes the fuel rods of contemporary light-water reactors.