Published 1997 | Version v1
Miscellaneous Open

A graphic simulation of the remote dismantling process of research nuclear reactors

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

A graphic simulation program is developed to assimilate the remote dismantling process of research nuclear reactors. This program makes extensive use of a commercial robot graphic instruction program. Firstly, a realistic graphic model of research reactors are built along with various dismantling equipments. Using the graphic instruction languages provided by IGRIP, then, a graphic process simulation program is developed that operates interactively with the user. Consequently, it is made possible for a process designer to visualize an arbitrary dismantling sequence and interactively modify the process. It is expected that the developed system will be utilized as an effective operator aid in both design and execution phases of remote dismantling of research reactor. (author) 7 refs., tabs., 6 figs

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Part of:
Proceedings of the 1st workshop on radioactive waste treatment technologies, October 28, 1997 Taejon, Korea

Additional details

Publishing Information

Publisher
KAERI.
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the 1st workshop on radioactive waste treatment technologies, October 28, 1997 Taejon, Korea
Imprint Pagination
286 p.
Journal Page Range
p. 175-183.
Report number
INIS-KR--005

Conference

Title
1. workshop on radioactive waste treatment technologies.
Dates
28 Oct 1997.
Place
Taejon (Korea, Republic of).

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
29018545
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER GRAPHICS; COMPUTERIZED SIMULATION; REACTOR DECOMMISSIONING; REACTOR DISMANTLING; REMOTE HANDLING; RESEARCH REACTORS; ROBOTS
Descriptors DEC
DECOMMISSIONING; DEMOLITION; EQUIPMENT; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION

Optional Information