Development of animation and simulation module for evaluation of Worker's dose
Creators
- 1. Korea Atomic Energy Research Institute, Yuseong-gu, Daejeon (Korea, Republic of)
- 2. Chungnam National Univ., Dept. of Computer Science, Yuseong-gu, Daejeon (Korea, Republic of)
Description
A study to visualize the radioactivity distribution in a dismantling facility that was contaminated by the radiation from the exposure room at KRR 2(Korean Research Reactor TRIGA MARK III) was carried out to improve worker safety and decommissioning productivity. As a basic study to minimize a radiation exposure, the worker exposure dose was calculated using the MCNP-4C (Monte Carlo N-Particle-4C). Secondly, an animation and simulation module was implemented to simulate a worker's real-time dose. The results show that various kinds of dismantling activities can be simulated while simultaneously viewing the exposure dose in a real-time according to the selected scenario for the animation. Current work is focus on exploring the evaluation of a worker's dose in a virtual dismantling area by using computer graphics. Future work will seek an optimization of the major parameters that directly affect a personnel exposure dose rate. This will enable a worker who is engaged in a hazardous area to attain an improve safety by decreasing exposure when applied as a useful tool to dismantle nuclear facilities. (authors)
Availability note (English)
Available from: WM Symposia, 1628 E. Southern Avenue, Suite 9 - 332, Tempe, AZ 85282 (US); also available online at: http://www.wmsym.org/archives/2007/search.htmlAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- INIS-US--09-WM-07195
Conference
- Title
- 2007 Waste Management Symposium - Global Accomplishments in Environmental and Radioactive Waste Management: Education and Opportunity for the Next Generation of Waste Management Professionals
- Acronym
- WM'07
- Dates
- 25 Feb - 1 Mar 2007
- Place
- Tucson, AZ (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 41038217
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DECOMMISSIONING; DOSE RATES; EVALUATION; MONTE CARLO METHOD; OCCUPATIONAL SAFETY; PERSONNEL; RADIATION DOSES; RADIOACTIVITY; SIMULATION; TRIGA-2-SEOUL REACTOR
- Descriptors DEC
- CALCULATION METHODS; DOSES; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs.