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Russian nuclear microreactor Shelf-M. A nuclear microreactor is a type of nuclear reactor which can be easily assembled and transported by road, rail or air. [1] Microreactors are 100 to 1,000 times smaller than conventional nuclear reactors, and range in capacity from 1 to 20 MWe (megawatts of electricity), compared to 20 to 300 MWe (megawatts of electricity) for small modular reactors (SMRs ...
The reactor design is a fast-neutron reactor with heat pipe cooling similar to the NASA Kilopower reactor. [2] According to the designers, the reactor will have a "large negative temperature reactivity coefficient ", lacks pumps and valves, uses heat pipes for heat removal, has no nuclear refueling intervals and associated core exposure, and ...
Out of the initial three contracts - BWX Technologies, Westinghouse Government Services and X-energy - only BWX Technologies and X-energy were selected in 2021 to develop a final design for a prototype mobile microreactor under the Project Pele initiative, [4] and then in June 2022 BWXT was awarded a contract by the US Department of Defense (DOD) Strategic Capabilities Office (SCO) to build ...
The microreactor is usually a continuous flow reactor (contrast with/to a batch reactor). Microreactors can offer many advantages over conventional scale reactors, including improvements in energy efficiency , reaction speed and yield, safety, reliability, scalability, on-site/on-demand production, and a much finer degree of process control .
Heat from nuclear fission is passed to a working fluid coolant. In commercial reactors, this drives turbines connected to electrical generator shafts. The heat can also be used for district heating, and industrial applications including desalination and hydrogen production. Some reactors are used to produce isotopes for medical and industrial use.
The high operating temperatures of HTGR reactors potentially enable applications such as process heat or hydrogen production via the thermochemical sulfur–iodine cycle. A proposed development of the HGTR is the Generation IV very-high-temperature reactor (VHTR) which would initially work with temperatures of 750 to 950 °C.
It is a helium gas cooled reactor. The reactor is contained in one vessel, with all of the coolant and heat transfer equipment enclosed in a second vessel, attached to the reactor by a single coaxial line for coolant flow. The plant is a four-story, entirely above-ground building with a 10–25 MWelectrical output. The helium coolant doesn't ...
Pool type sodium-cooled fast reactor (SFR) A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor.