Results 1 - 10 of 95
Results 1 - 10 of 95. Search took: 0.031 seconds
|Sort by: date | relevance|
[en] LMR is the reactor type that makes utilization of uranium resource very efficiently and the necessity of construction of a LMR in 2020's has been raised. However, the design technology required for construction has not been secured domestically. To fulfill the necessity, study has been made for the LMR system design technology and conceptual design of KALIMER systems for fluid, instrumentation, control, and protection have been developed. Also the computer code systems for the design and analysis of the KALIMER fluid systems have been developed. These study results are to used as the starting point of the next phase LMR design technology development research
[en] In this study, all the R and D projects of KAERI based on the national 'mid- and long-term nuclear energy R and D program' were classified into 'top-priority projects', 'core projects', 'basic and fundamental projects' and 'preceding projects' according to the time-depending importance and the characteristics of R and D projects. This study also suggested the differential support of R and D resources among projects on the basis of the new classification. It should be required the cooperation and support of the domestic nuclear family for KAERI to be regenerated into the internationally excellent institute through the new R and D policy. It is also necessary to be made a proper condition for the effective accomplishment off the new R and D policy, for example, an implementation of the policy under the full responsibility of KAERI. It is expected that the results of this study will be used as basic data for establishment of the KAERI's long-term vision and the planning of the national nuclear energy R and D program, and reflected in the national nuclear energy R and D policy
[en] The major objective of this work is tow-fold: one is to develop a methodology to determine the best VHTR types for the nuclear hydrogen demonstration project and the other is to evaluate the various hydrogen production methods in terms of the technical feasibility and the effectiveness for the optimization of the nuclear hydrogen system. Both top-tier requirements and design requirements have been defined for the nuclear hydrogen system. For the determination of the VHTR type, a comparative study on the reference reactors, PBR and PBR, was conducted. Based on the analytic hierarchy process (AHP) method, a systematic methodology has been developed to compare the two VHTR types. Another scheme to determine the minimum reactor power was developed as well. Regarding the hydrogen production methods, comparison indices were defined and they were applied to the IS (Iodine-Sulfur) scheme, Westinghouse process, and the, high-temperature electrolysis method. For the HTE, IS, and MMI cycle, the thermal efficiency of hydrogen production were systematically evaluated. For the IS cycle, an overall process was identified and the functionality of some key components was identified. The economy of the nuclear hydrogen was evaluated, relative to various primary energy including natural gas coal, grid-electricity, and renewable. For the international collaborations, two joint research centers were established: NH-JRC between Korea and China and NH-JDC between Korea and US. Currently, several joint researches are underway through the research centers
[en] The national long-term R and D program, updated in 1977, requires Korea Atomic Energy Research Institute (KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor (KALIMER), along with supporting R and D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 Mwe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self-consistent design meeting a set of major safety design requirements for accident prevention. Some of the current emphasis includes those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve extensive supporting R and D programs. This paper summarizes some of the results of conceptual engineering and design analyses performed for the safety of KALIMER in the area of inherent safety, passive decay heat removal, sodium water reaction, and seismic isolation. (author)
[en] The objectives of the project are to study thermal hydraulic characteristics of reactor primary system for the verification of the reactor safety and to evaluate new safety concepts of new safety design features. To meet the research goal, several thermal hydraulic experiments were performed and related thermal hydraulic models were developed with the experimental data which were produced through the thermal hydraulic experiments. Followings are main research topics; - Multi-dimensional Phenomena in a Reactor Vessel Downcomer - Condensation Load and Thermal Mixing in the IRWST - Development of Thermal-Hydraulic Models for Two-Phase Flow - Development of Measurement Techniques for Two-Phase Flow - Supercritical Reactor T/H Characteristics Analysis From the above experimental and analytical studies, new safety design features of the advanced power reactors were verified and lots of the safety issues were also resolved
[en] This report presents the results of scaling analysis on the integral test loop to simulate Korean PWR plants, which includes the scaling methodology, scaling priority and scaling distortion Based on the priority of the key test matrix, the scaling priority is drawn to apply to the design of the integral test loop. Scaling analysis on the test loop is done based on the design basis and performed by the so-called ''Modified Volume Scaling'' methodology. In the first stage of scaling analysis(global scaling), the specifications and capacity of the components in the major systems are determined by the volume scaling methodology. In the second stage of scaling, local phenomena scaling is performed on major thermal hydraulic phenomena in each component and reproduction of local thermal hydraulic phenomena is checked. According to the local phenomena scaling results, specifications and capacity of the components in a system are modified. Finally, scaling distortion, which might occur in a certain system, is analyzed. Scaling results in this report might be modified in the stage of detailed design of the integral test loop, which will be carried out in near future. More comprehensive analysis on scaling distortion shall be carried out based on manufacturing specifications and performance verification test results of the integral test loop
[en] In order to inspect any marine or agricultural products that are suspected to be contaminated by radioactive materials, an automatic inspection system is to be developed. First, Physicochemical characteristics of inspecting items are investigated. Second, maximum permissible radioactivity in the food regulated by the Korean food regulation are surveyed, and it is calculated the inspection possibility with MCNP code in a designated short time by the automatic inspection system. Optimum detection time and operating condition are also studied. The inspection system is divided into three parts; radioactivity detection device, process control, machineries for moving and measuring. Each system developed separately and designed.
[en] High temperature creep-fatigue crack initiation and growth test facility was established and the test procedure was explained in detail. The tubular specimen including a machined defect made of Mod.9Cr-1Mo steel was used to observe the creep-fatigue crack initiation and growth behavior. An ultra long working distance zoom microscope was installed to observe the defect area directly in real-time and DCPD(direct current potential drop) apparatus was used to measure the crack growth. Total 15 specimens have been tested and the related output data such as temperature distribution, load, displacement, strain, voltage change across the defect, and captured photos were successfully obtained through tests. A thorough investigation of the collected data and the corresponding numerical analysis will be performed to increase the capability of the results
[en] The national energy demand is taking a sharp rise on account of the rapid growth of economy in Korea. Unfortunately, Korea has not much choice of alternative energy a promising option for Korea. For instance, eleven nuclear plants are in operation and 7 plants are under construction. Several plants are in planning stage. KAERI has played a major role in the design and operation of the plants in Korea. The spent fuel issue is calling for acute attention nationwide as the number of plants increases. Korea is actively seeking a technical solution to that problem surfacing on the horizon. A preliminary conceptual study on the P and T technology was performed from 1992 to 1996 and the future research directions were derived from that study. Because of the situation Korea is facing with, one of the major technical guidelines is that the P and T technology should be developed in compliance with the NPT. The concept of an accelerator driven subcritical system was found to be the most favorable option according to the conceptual study. KAERI set up an ambitious accelerator driven system development program for next 10 years. Key elementary technologies for a high current accelerator and a subcritical system are scheduled to be developed and experimented for the first five years (1997-2001). For the second five years (2002-2006), the accelerator program is pushed for the completion to parameters of 1 GeV, 20mA with capability to drive a subcritical system. For the subcritical system, a detail design study is to be performed and a small mockup system is to be built for bench scale test purpose
[en] The Quality Assurance system should play an importance role in order to create safety operation. And management of KNICS R and D should have strong leadership to build he safety mind and quality mind. Quality assurance system can help to develop safety management system and to create a positive safety culture in operating organization of nuclear development. The establishment and implementation of QA system is prerequisite for achieving goals of the worker's health, quality, environment and public acceptance in operation of nuclear facilities whether they are regulated by the governmental requirements or not. The focus of nuclear QA system is brought on establishment of an appropriate system and assurance of implementation of the system by continuous improvement of quality problems. As for QA activities related to nuclear R and D, we set up QA systems and supported implementation of the system. We conducted periodic audit of KNICS projects related to safety system development and took corrective actions according to the result. Radiation exposure riskiness of the KAERI's nuclear facilities is lower than that of nuclear power plant and they are more safe. But their safety have being supervised by regulatory body in compliance with laws and technical requirements of nuclear power plant. The present QA system should be changed to an integrated safety management system where elements of environment management, safety management and quality management are complimentarily interacting, and thus meet legal requirements. It is necessary to compare subsystems with KNICS QA and management system requirements to improve the effectiveness of existing implementing procedures in other KNICS projects.