Development of Computer Systems for Planning and Management of Reactor Decommissioning
スポンサーリンク
概要
- 論文の詳細を見る
The computer systems for planning and management of reactor decommissioning were developed for effective implementation of a decommissioning project. The systems are intended to be applied to construction of work breakdown structures and estimation of manpower needs, worker doses, etc. based on the unit productivity and work difficulty factors, which were developed by analyzing the actual data on the JPDR dismantling activities. In addition, information necessary for project planning can be effectively integrated as a graphical form on a computer screen by transferring the data produced by subprograms such as radioactive inventory and dose rate calculation routines among the systems. Expert systems were adopted for modeling a new decommissioning project using production rules by reconstructing work breakdown structures and work specifications. As the results, the systems were characterized by effective modeling of a decommissioning project, project management data estimation based on feedback of past experience, and information integration through the graphical user interface. On the other hands, the systems were validated by comparing the calculated results with the actual manpower needs of the JPDR dismantling activities; it is expected that the systems will be applicable to planning and evaluation of other decommissioning projects.
- 2001-03-25
著者
-
Yanagihara Satoshi
Japan Atomic Energy Research Institute
-
Shiraishi Kunio
Japan Atomic Energy Research Institute
-
SUKEGAWA Takenori
Japan Atomic Energy Research Institute
-
Yanagihara S
Japan Atomic Energy Res. Inst. Ibaraki‐ken Jpn
関連論文
- Systems Engineering for Decommissioning the Japan Power Demonstration Reactor
- Development of Computer Systems for Planning and Management of Reactor Decommissioning
- Development of remote surveillance squads for information collection on nuclear accidents
- Mobile robot with a self-positioning system
- Cladding embrittlement and fuel rod failure threshold under reactivity initiated accident condition.