A document control system (DCS), ANSIM (KAERI Advanced Nuclear Safety Information Management) was designed for the purpose of documents preparation, review, and approvement for JRTR (Jordan Research and Training Reactor) project. The ANSIM system consists of a document management, document container, project management, organization management, and EPC (Engineering, Procurement and Construction) document folder. The document container folder run after specific contents, a revision history of the design documents and drawings are issued in KAERI. The EPC document work-scope is a registry for incoming documents in ANSIM, the assignment of a manager or charger, document review, preparing and outgoing PM memorandum as attached the reviewed paper. On the other hand, KAERI is aiming another extra network server for the NRR (New Research Reactor) by the end of this year. In conclusion, it is the first, computation system of DCS that provides document form, document number, and approval line. Second, ANSIM increases the productivity of performance that can be recognized the document work-flow of oneself and all participants. Finally, a plenty of experience and knowledge of nuclear technology can be transmitted to next generation for the design, manufacturing, testing, installation, and commissioning. Though this, ANSIM is expected to allow the export of a knowledge and information system as well as a research reactor.

The supercritical carbon dioxide Brayton cycle(S-CO2) is one of promising alternatives as a power conversion system of the sodium-cooled fast reactor due to higher cycle efficiency and less reactive working fluid to sodium, compared to the steam Rankine cycle. In a S-CO2 Brayton cycle, turbine, compressors and generator are coupled with a same axis and their rotating speeds are variable in accordance with electrical outputs. However, to synchronize the cycle with a electrical grid, the electrical output of the cycle must has the same frequency with the electrical grid regardless of amount of the turbine output. To deal with this problem, several methods were proposed but each method still has their own weaknesses. In this paper, a new idea will be presented. The idea that the generator with the two reverse rotors are introduced into S-CO2 Brayton cycle and it aims to produce a full range of electricity at a fixed frequency with high efficiency.

HANARO(High Flux Advanced Neutron Application Reactor) design was started from 1985 and was constructed in 1995 by KAERI(Korea Atomic Energy Research Institute). The document control book was written by hand and hard-copy was kept at that time. JRTR(Jordan Research and Training Reactor) was contracted for export to Jordan March 2010 by KAERI Consortium. This contract is a matter for congratulation of export of first made-in-Korea nuclear system. NRR(New Research Reactor) officially launched in April 2012. The document control system is controlled by PPM (Project Procedure Manual) and QAP(Quality Assurance Procedure) and ANSIM(KAERI Advanced Nuclear Safety Information Management) was built for JRTR. ANSIM system consists of the document management holder, document container holder and organization management holder. This system was registered about 2,000 design output like DDA(Document Distribution for Agreement), design documents, design drawings and project manger memorandum. The system design for JRTR was smoothly performed using ANSIM. NRR set to separated exclusive system that was based on JRTR ANSIM. Folder of nuclear laws, codes and standards was added to that system and those will be useful during designing. The project and quality assurance plans and procedures has been managed from design documents separately. Above all things, independent review and ALARA(As Low As Reasonably Achievable) review were operated for nuclear safety at ANSIM. And cover and body of design document were combined and backup system was established. After then, system upgrade and operation pursue the effect analysis by design change for accomplishment of the research reactor project.

The Project of Jordan Research and Training Reactor (JRTR) officially launched in Aug. 2010. JRTR is the first made-in-Korea nuclear system to be built abroad by year 2015, and Korea Atomic Energy Research Institute (KAERI) is responsible for the design o

In neutron beam research, it is necessary for the shielding block and experimental equipment a dance floor in a nuclear reactor to travel in a fixed direction with little friction. However, precise travel is difficult to achieve due to factors such as vibration or gear backlash. We have imported air bearings from more developed nations to perform the role of moving instruments. In the beginning, an air bearing for use in three-dimensional measuring instruments similar to an air bearing was used; however, the performance was found to be insufficient. Accordingly, we collected data and conducted reverse engineering on this type of thrust pad. Through this process, it was confirmed that two issues were influencing the performance: the slant of the bottom of the air bearing and the bottom outside edge of the air bearing plate. The air bearing begins to move at 5 bar and moves smoothly without interruption at 7 bar. The result of this process was the development of a thrust pad which is superior in performance to the imported product and is being used in neutron beam research. We anticipate that this air bearing which has been developed will be used for experimental equipment which requires this type of precision in the future.

The Cold Neutron Research Facility(CNRF) is being built to produce a cold neutron which has peculiar physical property. In-Pool Assembly(IPA) was manufactured in a domestic factory, which is composed of moderator cell, heat exchanger, vacuum chamber, joint flange assembly and bracket etc. We had difficulties with the mechanical fabrication process due to the thin moderator cell. The special flange for the double flexible piping was developed. The tests of moderator cell, heat exchanger, vacuum chamber, double flexible pipe and IPA include the pressure test, normal temperature leak test and low temperature leak test. The moderator cell and heat exchanger were tested in the severe environmental condition and the burst tests of moderator cell were carried out. Above all, the bursting point took place at the area of the 0.01mm thinner place. It shows that the severe environmental test affects the bursting strength. The double flexible pipe welding at the IPA top plate was related with the arrangement of moderator cell in the vacuum chamber. Therefore the connecting welding of the double flexible pipe linked to sequent of the vacuum piping, helium piping and hydrogen piping. The fabrication, test and assembling of cryogenic in radiation zone were developed.