[en] The AI-PLBR breeder plant design prepared for ERDA and EPRI is of 1000 MWe size, utilizing a loop-type sodium system configuration and producing 2200 psig/850⁰F steam. A 'bullseye' core geometry type sodium system configuration and is employed with Pu0₂-UO₂ fuel and UO₂ fertile material. The reactor outlet coolant temperature is 930⁰F. A modified 'A'-frame refueling system is employed, which is capable of handling 1/3 of a core loading in 12 days. An inducer-type mechanical pump is used in the primary circuit because of its excellent NPSH characteristics. Hockey sticks steam generators are used to produce near-fossil steam conditions at the turbine throttle. The balance of plant (BOP) design was developed by the architectural-engineering firm of Burns and Roe. It includes Allis-Chalmers - KWU 1800-rpm tandem-compound turbine, selected with high-,intermediate-, and two double-flow low-pressure cylinders equipped with two moisture separator cyclones. A design feature to enhance the licensability of the reference design is the three-level Decay Heat Removal System (DHRS), which consists of normal, backup, and diverse decay heat removal paths. The Atomics International PLBR design illustrated the technical soundness of the LMFBR system for meeting the world's long-term electrical energy supply needs. The design includes design features to assure licensability and innovative engineering features to enhance reliability, constructability, economics, and U.S. utility grid compatibility. The design concept provides a sound basis for the future detailed design of a prototype plant and subsequent development of larger LMFBR plants. (author)

[en] The background and current developments relating to the PLBR reactor are reviewed

[en] The optimization of the Westinghouse/Stone and Webster Prototype Large Breeder Reactor (PLBR) is described. This reactor plant, designed for ERDA and EPRI, resulted from optimization and tradeoffs on plant size, number of loops, steam cycles, system temperature, pump location, refueling concept, reactor shut-down system logic, control system logic, steam generating system, residual heat removal system, core arrangement and reactor vessel. The result is a three loop LMFBR rated at 1000 MWe gross with sodium entering the reactor vessel at 650⁰F (345⁰C) and leaving at 950⁰F) (510⁰C). The reactor vessel has a flat closure head on top, containing three rotating plugs on which are mounted the upper internals structure and the in-vessel transfer machine. The core has three radial layers of core material separating four radial blanket regions. An inclined refueling chute penetrates the reactor vessel. Plant efficiency of 37% is achieved with the use of once-through steam generators operating in the modified Sulzer mode, producing 2200 psi, 850⁰F (15.2 x 10⁶ pa/455⁰C) steam. The residual heat removal system (RHRS) consists of three independent heat removal paths in which the intermediate sodium is cooled in air blast heat exchangers (author)

[en] The General Electric/Bechtel PLBR is a conservatively designed 1000 MWe gross (914 MWe net) plant which gives confidence that a practical LMFBR can be built for U.S. application. A significant finding is that the LMFBR achieves lowest costs with a low reactor outlet temperature (468⁰C) and a low pressure (6.89 x 10⁶ Pa) saturated steam cycle. Moreover, the risks of failing to meet performance or other goals are lower for these cycle conditions than for higher temperature superheat cycle conditions. (author)

No abstract available

[en] The SNR-300 in Kalkar was considered to be an important project in European fast breeder development. The nuclear power plant was financed, developed and built in a joint German-Belgian-Netherlands collaborative effort, and was ready technically in June 1986 to accomodate the fuel assemblies and for the start of nuclear commissioning. Although the decision to not start up the SNR-300 de facto means opting out of a long term scheme of European collaboration in the development of breeder reactors, and the failure to abide by contractual agreements has financial consequences for Germany, the SNR-300 project was discontinued for political reasons in March 1991. (orig.)

No abstract available

[en] The prototype large breeder reactor (PLBR) is a 1000 MWe sodium cooled fast breeder reactor designed to succeed the Clinch Breeder Reactor and verify scaling laws. Several conceptual PLBR designs have been presented for consideration. A procedure is needed for the conceptualization of, evaluation of, and selection between such designs. This paper presents a method that can be effectively used to: (1) allocate optimal component redundancy, (2) evaluate design trade-offs, and (3) help in design finalization. The procedure is applied to three diverse design options for a shutdown heat removal system (SHRS). The selected configuration is analyzed for potential common cause failures

[en] A critical analysis of the core/blanket complex as defined in the Phase A LMFBR Pool Guidelines was performed with respect to consistency and feasibility of the nuclear, thermal and mechanical design assumptions. Recommendations were made for changes in fuel assembly and blanket assembly design, core configuration and orificing

[en] Commercial acceptance of the liquid metal reactor had its beginning with the Fermi reactor, over two decades ago. The pattern of industrialization since that time is discussed, contrasting domestic and foreign experience. The recent termination of the Clinch River reactor project marks a watershed in the U.S. approach towards commercialization. The increased emphasis on achieving cost competitive designs reflects an awareness that barriers to industrialization are institutional and financial, and not technological