• Title/Summary/Keyword: Advanced Spent Fuel Conditioning Process (ACP)

Search Result 33, Processing Time 0.045 seconds

Application of the Digital Mockup to Preliminary Analysis the Remote Maintainability of ACP

  • Song, Tai-Gil;Kim, Sung-Hyun;Park, Byung-Suk;Yoon, Ji-Sup;Lee, Sang-Ho
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 2004.08a
    • /
    • pp.363-366
    • /
    • 2004
  • KAERI is developing the Advanced Spent Fuel Conditioning Process (ACP) as a pre-disposal treatment process for spent fuel. In this process, the management process must operate in intense radiation fields as well as in a high temperature. Therefore, remote maintenance has played a significant role in this process. Hence suitable remote handling and maintenance technology needs to be developed along with the design of the process concepts. To do this, we developed the digital mockup for the ACP. The digital mockup provides the capability of verifying the remote operability of the process without fabrication of the process equipment. In other words, by applying virtual reality to the remote maintenance operation, a remote operation task can be simulated in the digital mockup. Through utilizing this graphic simulation in this digital mockup, general guidelines can be established for designing equipment intended for remote handling and maintenance. Also, the designer of the equipment that must be remotely maintained should ensure that there is adequate access to the process equipment. The graphic simulator will substantially reduce the cost of the develo363pment of the remote handling and maintenance procedure as well as the process equipment.

  • PDF

Development of the Interface Module for an Effective Application of a Digital Mockup

  • Song, Tai-Gil;Kim, Sung-Hyun;Lim, Gwang-Mook;Yoon, Ji-Sup;Lee, Sang-Ho
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 2005.06a
    • /
    • pp.2407-2409
    • /
    • 2005
  • As the cumulative amount of spent fuel increases, the reliable and effective management of the spent fuel has become a world-wide mission. For this mission, KAERI is developing the Advanced Spent Fuel Conditioning Process (ACP) as a pre-disposal treatment process for spent fuel. Conventional approach to the development of the process and the remote operation technology is to fabricate the process equipment on the same scale as the real environment and demonstrate the remote handling operation using simulated fuel called a mock-up test. But this mock-up test is expensive and time consuming, since the design may need to be modified and the equipment fabricated again to account for the problems found during a testing. To deal with this problem, we developed a digital mockup for the ACP. Also, for an effective utilization of the digital mockup, we developed user interface modules such as the data acquisition and display module and the external input device interface module. The result of this implementation shows that a continuous motion of the manipulator using the external device interface can be represented easily and the information display screens responded well to the simulation situation.

  • PDF

Analysis of Remote Operation involved in Spent Nuclear Fuel Conditioning Process using its Virtual Mockup

  • Yoon, Ji-Sup;Kim, Sung-Hyun;Song, Tai-Gil
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 2004.08a
    • /
    • pp.840-845
    • /
    • 2004
  • The remote operation of the Advanced Spent Fuel Conditioning Process (ACP) is analyzed by using the 3D graphic simulation tools. Since the spent nuclear fuel, which is a high radioactive material, is processed in the ACP, the ACP equipment is operated in intense radiation fields as well as in a high temperature. Thus, the equipment is operated in a remote manner and should be designed with consideration for the remote handling and maintenance. Also suitable remote handling technology needs to be developed along with the design of the process concepts. For this we developed a graphic simulator, which provides the capability of verifying the remote operability of the ACP without the fabrication of the process equipment. In other words, by applying virtual reality to the remote maintenance operation, a remote operation task can be simulated in the graphic simulator, not in the real environment. The graphic simulator will substantially reduce the cost of the development of the remote handling and maintenance procedure as well as the process equipment, while at the same time developing a remote maintenance concept that is more reliable, easier to implement, and easier to understand.

  • PDF

Graphic Simulator for Analyzing the Remote Operation of the Advanced Spent Fuel Conditioning Process

  • Song, Tai-Gil;Kim, Sung-Hyun;Lee, Jong-Ryul;Yoon, Ji-Sup
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 2003.10a
    • /
    • pp.1319-1322
    • /
    • 2003
  • KAERI is developing the Advanced Spent Fuel Conditioning Process (ACP) as a pre-disposal treatment process for spent fuel. Equipment used for such a spent fuel recycling and management process must operate in intense radiation fields as well as in a high temperature. Therefore, remote maintenance has a played a significant role in this process because of combined chemical and radiological contamination. Hence suitable remote handling and maintenance technology needs to be developed along with the design of the process concepts. To do this, we developed the graphic simulator for the ACP. The graphic simulator provides the capability of verifying the remote operability of the process without fabrication of the process equipment. In other words, by applying virtual reality to the remote maintenance operation, a remote operation task can be simulated in the graphic simulator, not in a real environment. The graphic simulator will substantially reduce the cost of the development of the remote handling and maintenance procedure as well as the process equipment, while at the same time producing a process and a remote maintenance concept that is more reliable, easier to implement, and easier to understand.

  • PDF

Visualization and Analysis of Remote Operation involved in Advanced Conditioning Process

  • Yoon, Ji-Sup;Kim, Sung-Hyun;Song, Tai-Gil
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2004.02a
    • /
    • pp.205-219
    • /
    • 2004
  • The remote operation of the Advanced Spent Fuel Conditioning Process (ACP) is analyzed by using the 3D graphic simulation tools. The ACP equipment operates in intense radiation fields as well as in a high temperature. Thus, the equipment should be designed in consideration of the remote handling and maintenance. As well as suitable remote handling and maintenance technology needs to be developed along with the design of the process concepts. To develop such remote operation technology, we developed the graphic simulator which provides the capability of verifying the remote operability of the ACP without fabrication of the process equipment. In other words, by applying virtual reality to the remote maintenance operation, a remote operation task can be simulated in the graphic simulator, not in the real environment. The graphic simulator will substantially reduce the cost of the development of the remote handling and maintenance procedure as well as the process equipment, while at the same time developing a remote maintenance concept that is more reliable, easier to implement, and easier to understand.

  • PDF

A Bridge Transported Bilateral Force-Reflecting Servo-Manipulator for Maintenance of Nuclear Pyroprocessing Equipment

  • Park, B.S.;Jin, J.H.;Ko, B.S.;Lee, J.K.;Yoon, J.S.
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 2005.06a
    • /
    • pp.2226-2230
    • /
    • 2005
  • The Advanced Spent Fuel Conditioning Process (ACP), which is a pre-disposal treatment process for spent fuel is being developed at the Korea Atomic Energy Research Institute (KAERI). The ACP equipment is operated in an intense radiation field as well as in a high temperature. Thus, the equipment is designed in consideration of the remote handling and maintenance. This paper describes a Bridge Transported Bilateral Force-Reflecting Servo-Manipulator (BTSM) system, which is being developed to overcome the limitation of access that is a drawback of the mechanical Master-Slave Manipulators (MSMs), which are mounted on the ACP hot cell wall for the operation and the maintenance of the ACP equipment. The BTSM system was manufactured and temporally installed at the mockup to test its performance. The manufactured BTSM system will be installed at the ACP hot cell on June 2005 after the accomplishment of the performance test. The BTSM system consists of four components: a transporter with a telescoping tubeset, a slave manipulator, a master manipulator, and a remote control system. This system will highly increase the volume of coverage for the operation and maintenance of the ACP equipment.

  • PDF

Development of a Bridge Transported Servo Manipulator System for the Remote Operation and Maintenance of Advanced Spent Fuel Conditioning Process (사용후 핵연료 차세대관리공정 원격 운전/유지보수용 천정이동 서보 매니퓰레이터 시스템 개발)

  • Park, Byung-Suk;Lee, Jong-Kwang;Lee, Hyo-Jik;Choi, Chang-Hwan;Yoon, Kwang-Ho;Yoon, Ji-Sup
    • Journal of Institute of Control, Robotics and Systems
    • /
    • v.13 no.10
    • /
    • pp.940-948
    • /
    • 2007
  • The Advanced Spent Fuel Conditioning Process(ACP), which is the process of the reduction of uranium oxide by lithium metal in a high temperature molten salt bath for spent fuel, was developed at Korea Atomic Energy Research Institute (KAERI). Since the ACP equipment is located in an intense radiation field (hot cell) as well as in a high temperature, it must be remotely operated and maintained. The ACP hot cell is very narrow so the workspace of the wall-mounted mechanical Master-Slave Manipulators(MSMs) is restricted. A Bridge Transported Servo Manipulator(BTSM) system has been developed to overcome the limitation of an access that is a drawback of the mechanical MSMs. The BTSM system consists ot a bridge crane with telescoping tubeset, a slave manipulator, a master manipulator, and a control system. We applied a bilateral position-position control scheme with friction compensation as force-reflecting controller. In this paper, the transmission characteristics on the tendon-and-pulley train is numerically formulated and analyzed. Also, we evaluate the performance of the force-reflecting servo manipulator.

DEVELOPMENT OF HOT CELL FACILITIES FOR DEMONSTRATION OF ACP

  • You, Gil-Sung;Choung, Won-Myung;Ku, Jeong-Hoe;Cho, Il-Je;Kook, Dong-Hak;Park, Seong-Won
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2004.02a
    • /
    • pp.191-204
    • /
    • 2004
  • The research and development of effective management technologies of the spent fuels discharged from power reactors are an important and essential task of KAERI. In resent several years KAERI has focused on a project named "development and demonstration of the Advanced spent fuel Conditioning Process (ACP) in a laboratory scale." The Facility for ACP demonstration consists of two Hot Cells and auxiliary facilities. It is now in the final design stage and will be constructed in 2004. After construction of the facility the ACP equipments will be installed in Hot Cells. The ACP will be demonstrated by some simulated spent fuels first and then by spent fuels.

  • PDF

Development of Safeguards System for Advanced Spent Fuel Conditioning Process

  • Lee Tae-Hoon;Song Dae-Yong;Ko Won-Il;Kim Ho-Dong;Jeong Ki-Jeong;Park Seong-Won
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2005.06a
    • /
    • pp.426-427
    • /
    • 2005
  • Advanced Spent Fuel Conditioning Process (ACP) is a pyrochemical process in which the spent fuel of PWR is transformed into the uranic metal ingot. Through this process, which has been developed in KAERI since 1998, the radioactivity, the radiotoxicity, the heat and the volume of the PWR spent fuel are reduced by a quarter of the original. To demonstrate a lab-scale process and extract the data for the later pilot-scale process, a demonstration facility of ACP (ACPF) is under construction and the lab-scale demonstration is slated for 2006. To establish the safeguardability of ACPF, a safeguards system including a neutron counter based on non-destructive assay, which is named as ACP Safeguards Neutron Counter (ASNC), the ACP Safeguards Surveillance System (ASSS) which consists of two neutron monitors and five IAEA cameras, and Laser Induced Breakdown System (LIBS) have been developed and are ready to be installed at ACPF. The target materials of ACP to assay with ASNC are categorized into three types among which the first is the uranic metal ingot, the second is the salt waste and the last is $UO_2$ and $U_{3}O_8$ powders, rod cuts and hulls. The Pu content of process nuclear materials can be accounted with ASNC. The ASSS is integrated in the ACP Intelligent Surveillance Software (AISS) in which the IAEA camera images and background signals at the rear doors of ACPF are displayed. The composition of special nuclear materials of ACP can be measured with LIBS which can be a supporting measurement tool for ASNC. The conceptual picture of safeguards system of ACPF is shown in Fig. 1.

  • PDF

The MUF of a Pilot-Scaled ACP Facility and Its Sensitivity

  • W. I. Ko;D. Y. Song;Lee, S. Y.;Kim, H. D.;Park, S. W.
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2003.11a
    • /
    • pp.401-405
    • /
    • 2003
  • The Advanced Spent Fuel Conditioning Process (ACP) have been developed at the Korea Atomic Energy Research Institute (KAERI) as an alternative for the effective conditioning of spent fuel far long-term storage or/and eventual disposal. This paper addresses the safeguardability of a pilot-scaled ACP facility and its sensitivity analysis. For this, a conceptual process and its material flow are analyzed using experiences from conventional fuel cycles, and measurement methods and their uncertainties are assumed for calculating MUF (Material Uncounted For) standards deviation (SD), We concluded from the preliminary analysis of the MUF SD that the pilot-scaled ACP facility with capacity of 30 MTHM/year can meet the International Atomic Energy Agency (IAEA) safeguards goals.

  • PDF