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The blocks are stacked, surrounded by the reactor vessel into a cylindrical core with a diameter and height of 14 m × 8 m. [15] The maximum allowed temperature of the graphite is up to 730 °C. [16] The reactor has an active core region 11.8 m in diameter by 7 m height. There are 1700 tons of graphite blocks in an RBMK-1000 reactor. [14]
The nominal power rating for each set is 70 megawatts, which are the largest traction current motor-generator sets ever built. It feeds the 110 kV balanced line traction power network through appropriate transformers. Power can be transferred from the Block II nuclear generator over the 380 kV transmission network. [citation needed]
Godiva II was constructed inside a concrete building with 20-inch-thick (51 cm) walls and 8-inch-thick (20 cm) roof in a canyon a quarter-mile (400 m) away from the control room. [ 4 ] [ 5 ] In 1959, Los Alamos agreed to make Godiva II available to DOD contractors free of charge for two days each month, acknowledging its unique facility for ...
VVER is the Soviet designation for a pressurized water reactor.The number following VVER, in this case 440, represents the power output of the original design. The VVER-440 Model V213 was a product of the first uniform safety requirements drawn up by the Soviet designers.
Reactor fuel rods are fully immersed in water kept at (12,5 / 15,7 / 16,2 ) MPa (1812/2277/2349 psi) pressure respectively so that it does not boil at the normal (220 to over 320 °C [428 to >608°F]) operating temperatures. Water in the reactor serves both as a coolant and a moderator which is an important safety feature.
The integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor). IFRs can breed more fuel and are distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.
GE further developed the BWR-1 design with the 70 MW Big Rock Point (9×9, 11×11, 12×12) reactor, which (like all GE BWR models following Dresden 1) used the more economical direct cycle method of heat transfer, but disposed with the external recirculation pumps in favor of natural circulation (an unusual strategy that only the 55 MW ...
On 29 March, Richard Lahey, former head of safety research for boiling-water reactors at General Electric, speculated that the reactor core may have melted through the reactor containment vessel onto a concrete floor, raising concerns of a major release of radioactive material, while failing to divulge the report by Dale G. Bridenbaugh which ...
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