enow.com Web Search

Search results

  1. Results from the WOW.Com Content Network
  2. Fast fission - Wikipedia

    en.wikipedia.org/wiki/Fast_fission

    A fast neutron reactor uses fast neutrons, so it does not use a moderator. Moderators may absorb a lot of neutrons in a thermal reactor , and fast fission produces a higher average number of neutrons per fission, so fast reactors have better neutron economy making a plutonium breeder reactor possible.

  3. Fast-neutron reactor - Wikipedia

    en.wikipedia.org/wiki/Fast-neutron_reactor

    The BN-350 fast-neutron reactor at Aktau, Kazakhstan.It operated between 1973 and 1994. A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors.

  4. BOR-60 - Wikipedia

    en.wikipedia.org/wiki/BOR-60

    Construction has started in 1964. Reactor reached first criticality in 1968. [4] Commissioned in 1969. [1] From 1969 to 1981 the BOR-60 used the pellet uranium fuel. [5] Since 1981 BOR-60 has been using the vibropac oxide mixed fuel with the power grade plutonium. [5] BOR-60 is expected to be closed in 2025. Currently constructed MBIR should ...

  5. Thermal-neutron reactor - Wikipedia

    en.wikipedia.org/wiki/Thermal-neutron_reactor

    A thermal-neutron reactor is a nuclear reactor that uses slow or thermal neutrons.. ("Thermal" does not mean hot in an absolute sense, but means in thermal equilibrium with the medium it is interacting with, the reactor's fuel, moderator and structure, which is much lower energy than the fast neutrons initially produced by fission.)

  6. Lead-cooled fast reactor - Wikipedia

    en.wikipedia.org/wiki/Lead-cooled_fast_reactor

    Reactors that use lead or lead-bismuth eutectic can be designed in a large range of power ratings. The Soviet union was able to operate the Alfa-class submarines with a lead-bismuth cooled intermediate-spectrum reactor moderated with beryllium from the 1960s to 1998, which had approximately 30 MW of mechanical output for 155 MW thermal power (see below).

  7. Sodium-cooled fast reactor - Wikipedia

    en.wikipedia.org/wiki/Sodium-cooled_fast_reactor

    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.

  8. Nuclear microreactor - Wikipedia

    en.wikipedia.org/wiki/Nuclear_microreactor

    The reactor core is surrounded by a thick shield to protect workers and the environment from radiation. The core also contains fuel rods that contain uranium or other fissile materials. As the fuel undergoes fission, it releases energy in the form of heat, which is then transferred to a coolant that circulates through the reactor.

  9. Prototype Fast Breeder Reactor - Wikipedia

    en.wikipedia.org/wiki/Prototype_Fast_Breeder_Reactor

    Main parameters of the reactor core; Fuel (fissile material) Plutonium/ 235 U [2] Fuel state: Solid: Neutron energy spectrum: Fast: Primary control method: Control rods: Primary coolant: Liquid sodium: Reactor usage; Primary use: Breeding of 233 U for AHWR-300 and generation of electricity: Power (thermal) 1253: Power (electric) 500