« PreviousContinue »
MODIFICATION NO. 1
DESCRIPTION OF LNFBR DEMONSTRATION PLANT FACILITY AND SITE
Overall Description of the Plant
A-1.1 The LMFBR Demonstration Plant will be an integrated electric power plant and will include (a) a liquid sodium cooled reactor and steam generation system; (b) a steam turbine driven electric generation system; (c) heat rejection system; (d) electrical switchyard; and (e) related auxiliaries and supporting structures and facilities. The reactor will utilize liquid sodium as the coolant and will produce about 1,000 megawatts of thermal energy in the form of superheated steam at about 900°F. The active region of the core will be made up of fuel assemblies containing mixed plutonium-uranium oxide fuel clad in stainless steel. The fuel region will be surrounded by blanket assemblies similarly clad but containing fertile uranium-238.
A-1.2 The overall steam cycle will be similar to that of modern, conventional, steam-electric power plants. A simplified flow diagram with representative parameters for an LMFBR Demonstration Plant is shown in Figure 1. A simplified sketch of one possible arrangement of one of the primary coolant loops is shown in Figure 2.
A-1.3 The liquid sodium will be heated in the reactor core and will leave the reactor at about 1000°F; the sodium in the primary system will be radioactive due to neutron activitation and dissolved radioactive fission and corrosion products. The primary system will be located in an inert atmosphere in shielded vaults within a containment structure. Intermediate heat exchangers will be used to transfer heat to a nonradioactive secondary sodium coolant system for generation of steam at about 900°F to drive the turbine-generator. The exhaust steam from the turbine will be condensed by transferring its heat energy through the walls of condenser tubing to cooling water flowing on the other side. The condensate (water from condensed steam), is pumped through feedwater heaters where it is preheated and then pumped back into the steam generator. The specific method of providing a cooling water supply for the condenser will depend in large measure on the results of specific site environmental studies. The electrical energy generating efficiency of this Plant is expected to be in the range of 35 to 40 percent, which is typical of modern fossil fired plants.
A-1.4 Design guidelines for the Demonstration Plant stress maximum use of existing technology to reduce technical risks and assure safe, reliable operation. The Plant will be designed to operate reliably, safely and with minimum environmental effects in compliance with these guidelines. The design effort will be supported by a strong research and development program with significant emphasis on proof-testing. Major safety features of the Demonstration Plant nuclear steam supply system will include: duplicate and independent shutdown systems; a monitoring system that can sense abnormalities; a low pressure coolant system; and guard vessels surrounding the reactor vessel and other main coolant system components and primary piping so that the reactor core will remain immersed in sodium coolant even if there should be a break in the reactor vessel or main coolant system. Additional major safety features are the capability to remove core decay heat by natural circulation of sodium in the primary and intermediate loops in the event of loss of electrical (pumping) power, and a separate containment structure; a conceptual version of the containment is shown in Figure 3.
A-1.5 The major objectives of the demonstration Project are stated in the preamble of this contract. The manner in which the Demonstration Plant is operated, after the initial period of startup and testing, will be as similar as practicable to the commercial LMFBR plants that are expected to be operated in the 1980s. Except for research and development requirements that are a part of the planned program, every effort will be made to sustain a high plant load factor.
A-1.6 Although the specific design for the first Demonstration Plant has not been selected on a firm basis, a list of several key design parameters is shown in Figure 4.
A-2.1 The issS includes the following nuclear plant components, systems, equipment and structures.
A-2.1.1 Reactor core which includes the fuel, blanket, control and special assemblies and other in-vessel replaceable items such as core support, restraint, and instrumentation equipment and components.
Reactor vessel and cover.
Control drive mechanisms and operating
A-2.1.4 Handling devices for reactor cover and in- , vessel components.
A-2.1.5 Sodium heat transport systems including primary and secondary sodium systems; sodium steam generation and protection systems.
A-2.1.6 Auxiliary systems including safeguards cooling systems, component heating and cooling systems, coolant supply systems, and recovery systems, cover gas supply and purification systems, radioactive waste collection, storage, treating and disposal systems, and sodium fire protection and alarm systems.
A-2.1.11 Temporary and special instrumentation for construction, preoperational startup and power tests.
A-2.1.12 New and spent fuel transfer, cleaning, examination, maintenance and shipping facilities and equipment.
A-2.1.13 Component inspection, cleaning, and maintenance and storage equipment.
A-2.1.17 All facilities, structures and appurtenances related to the above systems and equipment and required to provide steam under the appropriate conditions to the BOP.
A-3.1 The site for the plant will be a portion of an approximately 1364 acre tract of land on a peninsula on the clinch River in Roane County within the city limits of Guk Ridge, Tennessee, as shown in Figure 5. The tract is owned by the United States of America and is in the custody of TVA. The tract is generally bounded by the AEC's Oak Ridge Reservation, and the Clinch River. A portion of the tract is committed to use as an industrial park as indicated in Figure 5.