| Budget Amount *help |
¥3,700,000 (Direct Cost: ¥3,700,000)
Fiscal Year 2005: ¥600,000 (Direct Cost: ¥600,000)
Fiscal Year 2004: ¥3,100,000 (Direct Cost: ¥3,100,000)
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| Research Abstract |
The nuclear engineering facilities belonging to universities are being scrapped due to their aging and a shortage of running money. In addition, even some of the departments of nuclear engineering were demolished as a result of structural reforms that are going on national universities. In the present study, as a mean of overcoming these problems, a virtual nuclear reactor experiment simulator for educational purpose was developed using IT and WEB technology. Students can perform, virtually and remotely on their personal computers (PCs) with the simulator, almost the same experiments as those conducted in the "reactor laboratory course for students majoring in nuclear engineering with the Kyoto university critical assembly (KUCA)".
In the development of simulator, practical situations such that the experiments might be performed on various types of PCs that could have different operational systems (WIN, MAC and UNIX) or various kinds of computing power were taken into account. The devel
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oped simulator is composed mainly of two parts : (1) the part of manipulating it through Graphical User Interface (GUI) and that of evaluating core neutronic characteristics. These are summarized as follows :
A) [Development using the JAVA technology] The simulator was developed using the JAVA technology since programs described by it can work on any operational systems of PCs. Experiments can be performed by manipulating bottoms displayed on a PC display using a mouse. The core configuration, such as a pitch between fuel plates, the number of fuel frames, and the positions of neutron detectors, can be selected from a menu field on the display.
B) [Evaluation of core neutronic characteristics] The simulator incorporates a variety of features designed for reducing computational burden on a PC with which virtual experiments are performed. For this purpose, for all kinds of core configurations encountered in reactor experiments conducted in KUCA, their core neutronic characteristics were evaluated in advance and then tabularized as a database. Necessary information is retrieved from the database to the simulator. These neutronic characteristics were evaluated using Standard Reactor Analysis Code (SRAC) developed by the Japan Atomic Energy Research Institution and the modified neutron source multiplication method based on 3D eigenvalue and fixed source problems for neutron diffusion equations.
C) [Release on WEB] The developed simulator was released from a WEB site of the following URL : http://shima25g.qe.eng.hokudai.ac.jp/~verl/
D) [Presentation of the present study] The results were presented at the annual and autumn meetings of the Japan Atomic Energy Society (JAES) held in 2005 Less
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