[en] The Advanced Plant 1000 uses two Delta 125 steam generators, with each steam generator rated at 1707.5 MWt. The AP1000 Delta 125 steam generator design has many features that represent 'best practices' with respect to steam generator design and reliability and long-term performance. These features are summarized in this paper. (authors)

[en] Available turbine technologies for a High Performance Light Water Reactor (HPLWR) have been analysed. For the envisaged steam pressures and temperatures of 25 MPa and 500 deg. C, no further challenges in turbine technologies have to be expected. The results from a steam cycle analysis indicate a net plant efficiency of 43.9% for the current HPLWR design. (authors)

[en] Failure data retrieved from seven categories of I and C modules, indicators, sensors, controllers (on-off type and analog type), transmitters, recorders, and converters, in aged nuclear power plants were analyzed. The study relied on investigation of KHNP' I and C module trouble reports and relevant documents. In the assessment, it was found that failures indicators and on-off controllers are critical factors for reliable and economical nuclear plant operations, particularly in aged nuclear plants. (authors)

[en] In prospecting the role of nuclear energy in a future society, it is necessary to foresee the social attitudes towards energy, economy and environment, and to analyze their interactions with the exploitation of nuclear energy itself. As those issues, this article looks upon the change of the socio-economic environment, the concerns about nuclear power and eco-environment, and the sustainability and limits of the energy resources, etc. With this perception, the so-called SWOT analysis is employed to identify the internal strengths (S) and/or weaknesses (W) of nuclear energy compared with other energy competitors on the basis of the evaluation of the external factors which are likely to play the roles of opportunities (O) for and/or threats (T) against the technological change in nuclear energy. (authors)

[en] Transition to coolant of supercritical parameters allows for principle engineering-and-economic characteristics of light-water nuclear power reactors to be substantially enhanced. Russian experience in development of channel-type reactors with supercritical water coolant has demonstrated advantages and practical feasibility of such reactors. (authors)

[en] This is a case study of the NuMAC nuclear accountability system developed at a private fuel fabrication facility. This paper investigates nuclear material accountability and safeguards by researching expert knowledge applied in the system design and development. Presented is a system developed to detect and deter the theft of weapons grade nuclear material. Examined is the system architecture that includes: issues for the design and development of the system; stakeholder issues; how the system was built and evolved; software design, database design, and development tool considerations; security and computing ethics. (author)

[en] Because of analysis field to be wider and complicated is required, it faces up hardships due to the narrow analysis scopes and limited functions of current vendor code systems. To overcome it KEPRI develop the in-house safety analysis methodology based on the available exquisite codes. For the development, the RETRAN code was modified and coupled to compensate for the lack of capabilities. To estimate the feasibility of the methodology and code system, some reactivity insertion accidents were analyzed and compared with the results mentioned in final safety analysis report of the plant. (authors)

[en] Mass optimization calculations have been completed with the code ALKASYSSRPS for a small Rankine space power conversion system with a power of 100 kWe. The main parameter varied in this optimization was the condenser temperature;, but other parameters were studied, including materials used in the primary and secondary loops, radiator type, and the number of power conversion units. The optimum system (with the lowest mass) was calculated for the system employing the material T-111 in the primary and the secondary loops. (authors)

[en] The hydrogen removal system has been designed to ensure hydrogen safety during DBA and BDBA. The maximal hydrogen concentrations occur in the containment during severe accidents. The system includes a set of passive autocatalytic recombiners (PAR) located in different areas of the containment. The location and capacity of recombiners have been chosen on the basis of calculation analysis. The calculations have been fulfilled with use of Russian computer best-estimated codes. (authors)

[en] One approach to fission power system design uses alkali metal heat pipes for the core primary heat-transfer system. Heat pipes may also be used as radiator elements or auxiliary thermal control elements. This synopsis characterizes long-life core heat pipes. References are included where information that is more detailed can be found. Specifics shown here are for demonstration purposes and do not necessarily reflect current Nasa Project Prometheus point designs. (author)