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Yu-Yu Shen;Kuei-Jen Cheng;Hsoung-Wei Chou
- Nuclear Engineering and Technology
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- v.55 no.8
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- pp.3010-3016
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- 2023
In recent years, the development of radioactive waste containers for nuclear facility decommissioning and dismantling is a critical issue because the Taiwan domestic boiling water reactor nuclear power plant is going to be decommissioned. The main purpose of this research is to design a metal container that meets the structural requirements of related regulations. At first, the shielding analysis was performed by varying dimensions of radioactive waste to determine the storage efficiency of the container. Then, a series of structural analyses for operational and accidental conditions of the container with full load were conducted, such as lifting, stacking, and drop impact conditions. On the other hand, the field drop impact tests were carried out to ensure structural integrity. The present research demonstrates the structural safety of the developed container for decommissioned nuclear facilities in Taiwan.
https://doi.org/10.1016/j.net.2023.05.004 인용 PDF

Kim, Cheon-Woo;Kim, Ji-Yean;ChoI, Jong-Rak;Ji, Pyung-Kook;Park, Jong-Kil;Shin, Sang-Woon;Ha, Jong-Hyun;Song, Myung-Jae
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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- v.2 no.3
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- pp.175-180
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- 2004
In order to vitrify the combustible dry active waste (DAW) generated from Korean Nuclear Power Plants, a glass formulation development based on waste composition was performed. A borosilicate glass, DG-2, was formulated to vitrify the DAW in an induction cold crucible melter (CCM). The processability, product performance, and volume reduction effect of the candidate glass were evaluated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product of the glass product such as chemical durability, phase stability, and density was satisfactory. The vitrification process using the candidate glass was also evaluated assuming that it was operated as economically as possible.
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Atherton, Elizabeth;Mathieson, John
- Nuclear Engineering and Technology
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- v.39 no.6
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- pp.697-702
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- 2007
Radioactive waste has been produced in the UK for many decades. Since the 1950' s much of this has been associated with civil nuclear power production and the nuclear weapons programme. There have been a number of unsuccessful attempts in the UK since the 1980s to deal with the waste and find suitable sites for its disposal. However, the UK Government has addressed this and in 2001 introduced the "Managing Radioactive Waste Safely" programme. The aim of this was to make decisions on the long-term radioactive waste management policy through stakeholder engagement. In 2006, it adopted a policy of geological disposal for higher activity wastes and following further consultations, is now at the stage of choosing how that policy should be implemented.
https://doi.org/10.5516/NET.2007.39.6.697 인용 PDF KSCI