The current domestic policy flow towards nuclear decommissioning have difficult maintaining existing nuclear technologies and capabilities. Knowledge management has become an important project management execution process. The decommissioning research department of the Korea Atomic Energy Research Institute, which conducts decommissioning research and technology development, also attempted to develop a decommissioning project management information system using this knowledge management method. The decommissioning project management information system consisted of scope management, configuration management, organization and manpower management, schedule management, cost management, risk management, and stakeholder management. In this paper, we developed a document management system to perform the decommissioning of nuclear power plants in the process of constructing a project management system for dismantling nuclear facilities. The decommissioning project management system will be completed in stages by linking the history management platform and the process optimization platform based on the document management system.
According to the nuclear safety act, the enforcement regulations and the notification of the atomic energy commission, a preliminary decommissioning plan must be submitted at all domestic nuclear facilities. In accordance with this preliminary decommissioning plan, it is required to prepare eleven items from the outline of the decommissioning plan of the nuclear facility to the fire protection. Currently, the nuclear fuel cycle facility operated by the Korea Atomic Energy Research Institute (KAERI) consists of a radioactive waste form test facility (RWFTF), a post irradiation examination facility (PIEF), a radioactive waste treatment facility (RWTF), and a radioactive waste storage facility (RWSF). The decommissioning strategies, decommissioning methods and dismantling activities of these nuclear facilities are described in this paper. The scope of decommissioning, the dismantling method, the final conditions of the site, the management of radioactive waste, and the cost of decommissioning are established in the decommissioning strategy. The decommissioning schedule, work order, basic principle and technical feasibility are determined at the method of decommissioning. The disinfection techniques and activity plans for facilities and sites contaminated with radioactive materials are described at the dismantling activity. Therefore, this paper describes the concept of decommissioning of the nuclear fuel cycle facilities and prepares a preliminary decommissioning plan to be prepared afterwards.
Project management is a tool for smooth operation during a full cycle from the design to normal operation including the schedule, document, and budget management, and document management is an important work for big projects such as the JRTR (Jordan Research and Training Reactor). To manage the various large documents for a research reactor, a project management system was resolved, a project procedure manual was prepared, and a document control system was established. The ANSIM (Advanced Nuclear Safety Information Management) system consists of a document management folder, document container folder, project management folder, organization management folder, and EPC (Engineering, Procurement and Construction) document folder. First, the system composition is a computerized version of the Inter-office Correspondence (IOC), the Document Distribution for Agreement (DDA), Design Documents, and Project Manager Memorandum (PM Memo) works prepared for the research reactor design. Second, it reviews, distributes, and approves design documents in the system and approves those documents to register and supply them to the research reactor user. Third, it integrates the information of the document system-using organization and its members, as well as users’ rights regarding the ANSIM document system. Throughout these functions, the ANSIM system has been contributing to the vitalization of united research. Not only did the ANSIM system realize a design document input, data load, and search system and manage KAERI’s long-period experience and knowledge information properties using a management strategy, but in doing so, it also contributed to research activation and will actively help in the construction of other nuclear facilities and exports abroad.
The HANARO reactor constructed from Jan. 1985 to April 1995, and a major utilization system, the Cold Neutron Research Facility was completed Nov. 2010. The cold neutron research facility consists of a Cold Neutron Source, a process system, a neutron guide and a Spectrometer. A moderator is utilized to transform thermal neutrons into cold neutrons. A moderator cell accommodates the moderator. The inner assembly contains an aluminum moderator cell connected to a stainless steel heat exchanger by a bi-metallic transition joint. An In-Pool Assembly is welded to this inner assembly and a double flexible pipe, and a vacuum chamber is inserted. After HANARO reactor shutdown, the in-pool assembly was installed at a cold neutron hole in the reactor pool. We confirmed a precise installation by using an underwater TV camera for a nuclear reactor inspection. In-pool assembly connected to double flexible pipe each system in the Cold Neutron Research Facility. After cold neutron research facility operated, the reliability of vacuum system, helium refrigerator system, gas blanket system and hydrogen system for maintenance was confirmed.
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.
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.
The In-Pile Section(IPS) is located inside the reactor pool. It is divided into 3-parts; the in-pool pipes, the IVA(IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to keep the functionality of the reactor coolant pressure boundary. The IVA is manufactured by local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. A IVA has been manufactured by local technique and have finally tested under high temperature and high pressure. The IVA and piping did not experience leakage, as we have checked the piping, flanges, assembly parts. We have obtained good data during the three cycle test which includes a pressure test, pressure and temperature cycling, and constant temperature.
FTL(Fuel Test Loop) is a facility that confirms performance of nuclear fuel at a similar irradiation condition with that of nuclear power plant. FTL construction work began on August, 2006 and ended on March, 2007. During Construction, ensuring the worker's safety was the top priority and installation of the FTL without hampering the integrity of the HANARO was the next one. The installation works were done successfully overcoming the difficulties such as on the limited space, on the radiation hazard inside the reactor pool, and finally on the shortening of the shut down period of the HANARO. The Commissioning of the FTL is on due to check the function and the performance of the equipment and the overall system as well. The FTL shall start operation with high burn up test fuels in early 2008 if the commissioning and licensing progress on schedule.
The Fuel Test Loop(FTL) which is capable of an irradiation testing under a similar operating condition to those of PWR(Pressurized Water Reactor) and CANDU(CANadian Deuterium Uranium reactor) nuclear power plants has been developed and installed in HANARO, KAERI(Korea Atomic Energy Research Institute). It is consisted of In-Pile Section(IPS) and Out-of Pile System(OPS). The IPS which is localed inside the pool is divided into 3-parts; they are in-pool pipes, IVA(IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to keep the functionality of the reactor collant pressure boundary. The localization of the IVA is achieved by manufacturing through local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique of the instrument lines has been checked for its functionality and yield. A IVA has been manufactured by local technique and will be finally tested under out of the high temperature and high pressure test.
The nuclear fuel cladding temperatures of the HANARO fuel test loop have been calculated by MARS code for the large break loss-of-coolant accidents. Conservative method was used for the analysis of the loss-of-coolant accidents. Consequently, the maximum peak cladding temperature was predicted as 1235K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. This means that the cooling capability of the emergency cooling water system for the HANARO fuel test loop is sufficient for the large break loss-of-coolant accidents.
The conservative method on the analysis of loss-of-coolant accidents for the HANARO fuel test loop was established based on the guide of evaluation method for the emergency core cooling systems of pressurized light water reactors. The evaluation models, the Moody model for discharge rate calculation and the Baker-Just model for water-metal reaction calculation, were used. In order to calculate conservative peak cladding temperatures for accidents the multipliers to the correlations of heat transfer coefficients in the MARS were also introduced. Consequently it is found that the maximum peak cladding temperature predicted by using the conservative method is sufficiently greater than that calculated by using the best-estimated models.