[en] Special construction of a pressure-vessel for liquid metal cooled reactors, or for simulating the technical aspects of those arrangements. (J.K.)

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[en] In this article availability information contained within the Centralized Reliability Data Organization (CREDO) liquid-metal reactor (LMR) data base is presented, and the availability critical items lists are developed. Individual components are ranked in prioritized lists from worst to best performers from an availability standpoint. Availability, as used here, is assumed to be an inherent characteristic of the component and is not necessarily assumed to be related to plant operability

[en] The roof slab has a metallic annular envelope made of two shell rings and two plates filled with concrete. Cylindrical spaces are provided in the slab for the passage of the reactor components. A truncated shell ring is welded to the metallic envelope and constitutes the reinforcement element of this envelope. One shell ring separates the inner volume of the envelope in two parts; it is design with apertures to allow the passage of the reactor components. The invention can be applied more particularly to fast reactors cooled by liquid sodium

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[en] The need for power reactors operating on a closed fuel cycle is very broadly discussed in the article. A brief summary of the issues and economics is provided. The article focuses on safety issues related to nuclear catastrophes at power plants. Lead-cooled fast reactors are briefly described and proposed as a solution to plutonium waste and safety issues

[en] Nuclear power plants currently generate about 20% of the U.S. electrical energy. The expected growth of electricity demand in the U.S. of over two percent per year(1), retirement of older plants, and increasing concerns about the harm to the environment of fossil fuel burning for electrical power generation may result in orders for new nuclear power plants in the next decade. It is anticipated that these new nuclear plants will be powered mainly, if not solely, by light water reactors (LWR), since all commercial nuclear plants currently operating in the U. S. (more than a hundred plants delivering about 100 GWe) are of this type and they have an experience base of more than 30 years. In 1988 the U. S. Department of Energy (DOE) selected the PRISM (power reactor innovative small module) reactor concept, in conjunction with the IFR (integral fast reactor) metal fuel cycle as the reference concept for the U. S. Advanced Liquid Metal Reactor (ALMR) program. Arrangements have been initiated for substantial international participation in the program. An overall project goal is to demonstrate the safety and performance features of the ALMR by test of a full-size prototype reactor and thereby provide a basis for Nuclear Regulatory Commission (NRC) certification of the design shortly after 2000, preparatory to commercial use. This paper summarize the reference ALMR design, reflecting recent progress in the design particularly in safety-related aspect

[en] In this study, the modification work for a 3-D solid modeling of KALIMER-600(Korea Advanced Liquid Metal Reactor, 600MWe) conceptual design by using I-DEAS, a commercial solid modeling program, was carried out by reflecting the design change produced through the design feasibility study. Also, the structures and components are drafted based on the 3-Dimensional modeling data and it is expected to be utilized for the reference document of the demonstration sodium-cooled fast reactor. The component arrangement and structural concepts are maintained the established concepts but the locally modified design features of the structures are applied