• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.403-408
• /
• 1998

비가연성 방사성 폐기물로 발생되는 물질은 큰크리트, 유리, 석고, 철재류, 토사류 및 원자력발전소 계통에서 발생하는 필터류 등이며, 이들 폐기물 중 금속류를 제외한 물질들의 성분은 SiO$_2$가 60%이상, CaO 3～12%, $Al_2$O$_3$ 10% 미만으로 일반 유리의 성분과 유사하다. 따라서 이들 비가연성 방사성 폐기물을 최적의 흔합비로 용융하였을 경우 안정한 유리질의 고화체를 생성시킬 수 있다. 본 연구에서는 시료별로 조성이 다른 비가연성 모의 폐기물을 플라즈마 토치(60kW)와 용융로 등이 장착된, 시스템에서의 용융 실험을 통해 약 20%정도의 부피 감용효과가 있음을 밝혀냈고, 생성된 웅융 고화체에 대한 침출실험을 통하여 EPA의 규제치를 안정적으로 만족하는 건전성을 확인하였다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1999.05a
• /
• pp.316-316
• /
• 1999

• Proceedings of the Korean Nuclear Society Conference
• /
• 1999.10a
• /
• pp.279.2-279
• /
• 1999

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2003.11a
• /
• pp.48-53
• /
• 2003

The high temperature melting test for nonflammable wastes using a plasma torch was conducted. The AP-200L hollow cathode type plasma torch was installed at the pilot plasma melting furnace in NETEC. The surrogates were prepared to simulate concrete, soil and their mixture with steel. The experimental conditions such as feeding rate, the distance between melts surface and torch nozzle, torch rotation speed, gas flow rate and pressure in the furnace were decided. Basic parameters such as temperatures of cooling waters, off-gas and torch power were measured. The vitrified samples were analyzed by SEM/EDS.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.523-530
• /
• 2005

In this study, maximum exposure rate at DAW(Dry Active Waste) drum surface which is satisfying regulation limit was calculated for conceptual design of IP(Industrial Package). DAW can be classified as combustible and non-combustible waste and the calculation was conducted for single and mixed radionuclide for each type of waste. In case of combustible waste that mixed radionuclide is uniformly distributed, the maximum exposure rates at drum surface were 3.60E-01, 8.85E-01 and 1.27E+01 mSv/hr for IP Type 1, 2-a and 2-b, respectively. and 3.60E-01, 8.85E-01, 1.27E+01 mSv/hr for single radionuclide(Co-60). In case of non-combustible waste that mixed radionuclide is uniformly distributed, the maximum exposure rates at drum surface were 7.14E-01, 1.83E+00, 2.69E+01 mSv/hr for IP Type 1, 2-a and 2-b, respectively. and 7.13E-01, 1.81E-01, 2.62E+01 mSv/hr for single radionuclide(Co-60). Through this study, the maximum amount of DAW can be transported by IP was suggested as maximum exposure rate at drum surface and the calculation for the other types of waste will be conducted.

• Journal of the Korean GEO-environmental Society
• /
• v.10 no.3
• /
• pp.47-52
• /
• 2009

The comparative analysis on physico-chemical characteristics of municipal solid waste from dwelling site and landfill site were performed to provide the fundamental information of waste management in Chungju city. It was analysed and evaluated the bulk density, physical component, three major component, chemical component, and heating value of MSW. The physical components depended on the sampling site in dwelling site and landfill site. But, by the ultimate analysis, the chemical composition was almost similar to result for municipal solid waste from dwelling site and landfill site. Therefore, it is necessary to investigate the physical components according to sampling site for the MBT to introduce for combustible municipal solid waste pre-treatment, but it needs the chemical composition from landfill site to design the incinerator. The physical composition showed that the combustible and the noncombustible occupied 87.4% and 12.6% respectively. In case of three component analysis, the moisture, the combustible, and the ash were 27.6, 60.5, 11.9% respectively. The chemical composition through the element analysis were C (50.1%), H (6%), O (39.5%), N (1.9%), S (0.5%), and Cl (1.3%).

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.14 no.2
• /
• pp.169-178
• /
• 2016

The properties of wastes for melting need to be considered to minimize the maintenance of refractory and to discharge the molten slags smoothly from a plasma torch melter. When the nonflammable wastes from nuclear facilities such as concrete debris, glass, sand, etc., are melted, they become acid slags with low basicity since the chemical composition has much more acid oxides than basic oxides. A molten slag does not have good characteristics of discharge and is mainly responsible for the refractory erosion due to its low liquidity. In case of a stationary plasma torch melter with a slant tapping port on the wall, a fixed amount of molten slags remains inside of tapping hole as well as the melter inside after tapping out. Nonmetallic slags keep the temperature higher than melting point of metal because metallic slags located on the bottom of melter by specific gravity difference are simultaneously melted when dual mode plasma torch operates in transferred mode. In order to minimize the refractory erosion, the compatible refractories are selected considering the temperature inside the melter and the melting behavior of slags whether to contact or noncontact with molten slags. An acidic refractory shall not be installed in adjacent to a basic refractory for the resistibility against corrosion.

• The Korean Journal of Nuclear Medicine Technology
• /
• v.21 no.2
• /
• pp.13-27
• /
• 2017

Purpose In the procedure of domestic medical radioactive self-disposal, there are many requests of supplementation and difficulties on the screening process. In this regard, presentation of basic guideline will improve the work processing efficiency of medical institution radioactive waste. From 2015 to 2016, We reviewed and compared a supplementary requests of domestic fifteen medical institution radioactive self-disposal Plan & Procedure manual. In connection with this, we derive the details of the radioactive waste document based on the relative regulation of nuclear safety Act. The representative supplementary requests of Korea Institute of Nuclear Safety are disposal method of non-flammability radioactive waste, storage method of scheduled self-disposal waste, the legitimacy of self-disposal and pre-treatment of self-disposal, reference radioactivity of disused filter and output of storage period, attachment the evidential matter of measurement efficiency when using a gamma counter. Through establishing a medical radioactive waste guideline, we can clearly suggest a classification standard of radioactive nuclide and the type of occurrence. As a result, we can confirm the reduction of examination processing period while preparing a self-disposal document and there is no spending expenses for business agency. Also, the storage efficiency of facility will better and reduce the economic expenses. On the basis of this guideline, we will expect a contribution to the improvement of work efficiency for officials who has a working-level difficulty of radioactive waste self-disposal.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.10 no.4
• /
• pp.247-254
• /
• 2012

Vitrification technology has been widely applied as one of effective processing methods for wastes generated in nuclear power plants. The advantage of vitrifying for low- and intermediate-level radioactive wastes has a large volume reduction and good durability for the final products. Recently, a filter using on HVAC(Heating Ventilating & Air Conditioning System) is composed with media (glass fiber) and separator (aluminum film) has been studied the proper treatment technology for meeting the waste disposal requirement. Present paper is a feasibility study for the filter vitrification that developing of the glass compositions for filter melting and melting test for physicochemical characteristic evaluation. The aluminum metal of film type is preparing with 0.5 cm size for proper mixing with glass frit, glass fiber is also preparing with 1 cm size within crucible. The glass compositions should be developed considering molten glass are related with wastes reduction. Glass compositions obtained from developing on glass formulation are mainly composed of $SiO_2$ and $B_2O_3$ for aluminum metal. A variety of factors obtained from the glass formulation and melting test are reviewed, which is feeding rate and glass characteristics of final products such as durability for implementing the wastes disposal requirement.

• Journal of the Korea Organic Resources Recycling Association
• /
• v.18 no.2
• /
• pp.84-92
• /
• 2010

This research was conducted to investigate physico-chemical characteristics of municipal solid waste (MSW) generated from T City, Gangwon-do and leaching characteristics of the incineration ash. From the results, bulk density of MSW in T city was $231kg/m^3$. Combustible and incombustible components were in 94.0% and 6.0%, respectively. Food waste and papers in combustible component occupied 32.3% and 41.2%. Water, volatile solids, and ash content were 41.3%, 50.5%, and 8.2%. C, H, O, N, S, and Cl showed 51.4%, 6.3%, 26.7%, 1.1%, 0.2%, 0.5%, respectively. Low heating value (2,704 kcal/kg) of T city was similar to 2,764 kcal/kg of Chuncheon and was 1,000 kcal/kg higher than 1,467~1,584 kcal/kg of the past Kuro-gu and Koyang city. The specification of leaching characteristics of the incineration ash were within the Korean regulation standard.