In the cleanup system, foul water condenses from the gas during dewatering. A foul process water enters with oil and phenol from the gasifier washer-coolers. These foul waters contain dissolved H2S, NH3, CO2j and phenols. The water separated from the oil and phenol is returned to the washer-coolers where some additional makeup water is located. This makeup water evaporates and enters the cleanup systems with the saturated gas. The construction period for a large coal-fired electric generation facility of the type characterized here would take a total of seven years. This includes a two-year period of fairly low level of effort for site selection, design and preparation, and a five-year period of actual on-site construction. During the on-site construction period, an estimated 8.1 million person-hours of direct craft labor would be required. The operating personnel requirement (336 persons) for this plant were estimated from experience with conventional plants. 3.2.5 Light Water Reactor Power Plant The reference light water reactor (LWR) power plantl6“20 £s a 1250-MW single-unit facility consisting of a pressurized water reactor supplying superheated steam to a conventional turbine generator. Condenser cooling is accomplished with a cooling tower. The reference reactor as shown schematically in Fig. 3.9 was scaled up to 3750 MWt from a basic Westinghouse 3450-MWt design. At the present time, nuclear fuel is being discharged from reactors after an average burnup of 25,000 to 30,000 megawatt days per metric ton of fuel (MW-d/t). LWR technology has a goal^l of achieving 50,000 MW-d/t, and therefore this value was assumed to be achieved by the year 2000 for the purpose of this characterization . The nuclear steam supply system (NSSS) consists of a light-water- moderated nuclear reactor having a reactor core containing low-enriched uranium oxide fuel, approximately 4.15% U-235, in approximately 193 fuel assemblies. Loaded in the core are 98,000 kg of fuel. The core is refueled by replacing approximately one-third of the total set of fuel elements at roughly one-year intervals. The spent fuel is stored on site in a special fuel handling building. This building is also a repository for fresh fuel prior to its insertion in the core. The NSSS produces approximately 3750 MWt at nominal full power. The power generation system consists of the reactor core and vessel, its associated pressurizer, and four primary reactor coolant loops and four steam generators. Primary coolant (water) is heated from 295°C to 330°C by the nuclear reaction taking place in the core. The nominal coolant pressure is 15.5 x 10^ Pa (or N/m^). The high pressure is maintained in the primary system by a pressurizer to prevent boiling in the core. This hot water is then passed through the steam generators (u-tube heat exchangers) where water on the secondary side of the heat exchanger is heated to produce steam. Water on the primary side of the steam generator is returned to the core to be reheated to 330°C. Steam produced on the secondary side of the steam generator passes through the turbine generator power-conversion system. The turbine generators, at nominal rated power, produce 1250 MW. The condensate from the
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