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Buck, E. C.; Kim, C.-W.; Wronkiewicz, D. J.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
AbstractAbstract
[en] Alteration may be expected for spent nuclear fuel exposed to groundwater under oxidizing conditions such as that which exist at the proposed nuclear waste repository at Yucca Mountain, Nevada. The actinide elements released during the corrosion of spent fuel may be incorporated into the structures of secondary U6+ phases. The incorporation of transuranics into the crystal structures of the alteration products may significantly decrease their mobility. A series of precipitation tests were conducted at 90 C to determine the potential incorporation of Ce4+ and Nd3+ (surrogates for Pu4+ and Am3+, respectively) into uranyl phase. Dehydrated schoepite (UO3·0.8-1.0HP2O) was produced by hydrolysis of a uranium oxyacetate solution containing either cerium or neodymium. ICP-MS analysis of the leachant, leachate, and solid phase reaction products which were dissolved in a HNO3 solution indicates that 26 ppm of Ce was incorporated into dehydrated schoepite. ICP-MS results from the Nd-doped tests indicate significant neodymium incorporation as well, however, the heterogeneous distribution of Nd in the solid phase noted during the AEM/EELS examination implies that neodymium may not incorporate into the structure of dehydrated schoepite
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25 Aug 1999; 12 p; Migration '99; Lake Tahoe, CA (United States); 26 Sep - 1 Oct 1999; W-31109-ENG-38; Also available from OSTI as DE00011950; PURL: https://www.osti.gov/servlets/purl/11950-38dB8Y/webviewable/
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Report
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ACTINIDE COMPOUNDS, ACTINIDES, CHEMICAL REACTIONS, ELEMENTS, ENERGY SOURCES, ENVIRONMENTAL TRANSPORT, FUELS, HYDROGEN COMPOUNDS, MANAGEMENT, MASS TRANSFER, MATERIALS, METALS, MOUNTAINS, NUCLEAR FUELS, OXYGEN COMPOUNDS, RADIOACTIVE WASTE MANAGEMENT, RARE EARTHS, REACTOR MATERIALS, TRANSPLUTONIUM ELEMENTS, TRANSURANIUM ELEMENTS, URANIUM COMPOUNDS, WASTE DISPOSAL, WASTE MANAGEMENT, WATER
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Kim, C. W.; Wronkiewicz, D. J.; Buck, E. C.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
AbstractAbstract
[en] The UO2 in spent nuclear fuel is unstable under moist oxidizing conditions and will be altered to uranyl oxide hydrate phases. The transuranics released during the corrosion of spent fuel may also be incorporated into the structures of secondary U6+ phases. The incorporation of radionuclides into alteration products will affect their mobility. A series of precipitation tests were conducted at either 150 or 90 C for seven days to determine the potential incorporation of Ce4+ and Nd3+ (surrogates for Pu4+ and Am3+, respectively) into uranium phases. Ianthinite ([U24+(UO2)4O6(OH)4(H2O)4](H2O)5) was produced by dissolving uranium oxyacetate in a solution containing copper acetate monohydrate as a reductant. The leachant used in these tests were doped with either 2.1 ppm cerium or 399 ppm neodymium. Inductively coupled plasma-mass spectrometer (ICP-MS) analysis of the solid phase reaction products which were dissolved in a HNO3 solution indicates that about 306 ppm Ce (Kd = 146) was incorporated into ianthinite, while neodymium contents were much higher, being approximately 24,800 ppm (Kd = 62). Solid phase examinations using an analytical transmission electron microscope/electron energy-loss spectrometer (AEM/EELS) indicate a uniform distribution of Nd, while Ce contents were below detection. Becquerelite (Ca[(UO2)6O4(OH)6]·8H2O) was produced by dissolving uranium oxyacetate in a solution containing calcium acetate. The leachant in these tests was doped with either 2.1 ppm cerium or 277 ppm neodymium. ICP-MS results indicate that about 33 ppm Ce (Kd=16) was incorporated into becquerelite, while neodymium contents were higher, being approximately 1,300 ppm (Kd=5). Homogeneous distribution of Nd in the solid phase was noted during AEM/EELS examination, and Ce contents were also below detection
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7 Dec 1999; 10 p; Materials Research Society Annual Fall Meeting; Boston, MA (United States); 29 Nov - 3 Dec 1999; W-31109-ENG-38; Also available from OSTI as DE00750617; PURL: https://www.osti.gov/servlets/purl/750617-P1bC2X/webviewable/
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ACTINIDE COMPOUNDS, ACTINIDES, CHALCOGENIDES, CHEMICAL REACTIONS, DISSOLUTION, ELEMENTS, ENERGY SOURCES, ENVIRONMENTAL TRANSPORT, FUELS, MASS TRANSFER, MATERIALS, METALS, MINERALS, NUCLEAR FUELS, OXIDE MINERALS, OXIDES, OXYGEN COMPOUNDS, RADIOACTIVE MATERIALS, RADIOACTIVE MINERALS, RADIOACTIVE WASTES, RARE EARTHS, REACTOR MATERIALS, SEPARATION PROCESSES, TRANSPLUTONIUM ELEMENTS, TRANSURANIUM ELEMENTS, URANIUM COMPOUNDS, URANIUM MINERALS, URANIUM OXIDES, WASTES
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Kim, C.-W.
National regulatory authorities with competence in the safety of radiation sources and the security of radioactive materials. Proceedings2001
National regulatory authorities with competence in the safety of radiation sources and the security of radioactive materials. Proceedings2001
AbstractAbstract
[en] In this paper, the orphan source control programme in Korea will be discussed. Orphan sources are, in general, classified into three groups: 1) Illegally trafficking radioactive sources; 2) Domestic loss of radioactive sources due to the bankruptcy of licensees or authorized suppliers; and 3) Contaminated metal scrap, which has been imported. There are, currently, two approaches going on to control and manage orphan sources in Korea. First, the Korean regulatory authority (Ministry of Science and Technology: MOST) will fully run an information system on radiation safety to effectively trace and monitor all radioactive sources in the country by the year 2001. Second, the regulatory authority strongly advises steel mill companies to closely scrutinize and inspect scrap metal through a scrap monitoring system when they attempt to reutilize it in order to prevent it from being contaminated by uncontrolled sources. The Korea Institute of Nuclear Safety (KINS), a regulatory expert organization, is carrying out a three-year multiphase project to control and monitor orphan sources in Korea. The system, called the Information System on Integrated Radiation Safety (ISIRS) on the inter- and intra-net system has been developed to effectively control and accurately monitor radioactive sources on a real time basis since 1998. If the system is successfully set up as scheduled by the middle of May next year, the regulatory authority will be able to control any reutilization of uncontrolled sources efficiently. At the same time, the system can also provide, not only licensees, suppliers, or perspective end users but also the Korean general public of interests with information on radiation safety, safe radiation management tools and public services. The system has been created because of the necessity to effectively control radioactive sources safely. Also, it serves to prepare necessary protective measures in a timely manner for abnormal events of uncontrolled radiation from radioactive sources such as those involving loss of radioisotopes. By the 2001, the system will be able to provide both licensees and the general public with information on radiation safety more actively and effectively. At the same time, it will serve to guarantee the right to knowledge of the Korean people and to facilitate and effectuate the control of radioactive sources both by industry and by the regulatory authority. The system is composed of three parts; 'Information System on Regulatory Activities for Radioactive Sources including Radiation Generators', 'Cyber Information System Radiation Safety', and 'Radioactive Source Life-Cycle Tracking and Inventory Management System'. With this system, we are going to trace the life cycle of radioactive sources; enabling inventory, prophylactic measures for accidents or abnormal events such as from loss of radioactive sources, usage history, transportation, waste management, etc. Since the system traces radioactive sources 'from the cradle to the grave', we expect to prevent illegal trafficking of the radioactive sources. All steel mill companies and suppliers of scrap metals in Korea should install the Scrap Monitoring systems to detect the contamination of recycled metals in the nearest future. Currently, large numbers of major steel mill companies have installed fixed-type scrap monitoring systems and operate them to detect any contaminated scrap metals existed before melting for reutilization. They have detected radioactive substances in recycled scrap metals before melting more than 20 times since 1998. However, the levels of radioactivity were found to be very low. The orphan sources programme being developed in Korea will be a timely and efficient method for bringing orphan sources under control. The dissemination of information to the public and industry will increase awareness of the problem of orphan sources. The improved oversight of licensed devices by MOST will help reduce the number of sources that have become orphaned and MOST is encouraging the installation of additional fixed radiation monitoring systems at seaports and at other locations where radiation sources may appear. Finally, international action is necessary to control sources. (author)
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International Atomic Energy Agency, Vienna (Austria); 502 p; Aug 2001; p. 287-292; International conference of national regulatory authorities with competence in the safety of radiation sources and the security of radioactive materials; Buenos Aires (Argentina); 11-15 Dec 2000; IAEA-CN--84/43; ISSN 1563-0153; ; 2 figs, 2 tabs
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Choi, K.; Kim, C.-W.; Park, J. K.; Shin, S. W.; Song, M.-J.; Brunelot, P.; Flament, T.
Nuclear Environment Technology Institute Korea Hydro and Nuclear Power Company, Ltd. P.O.Box 149, Yusung, Taejon 305-600 (Korea, Republic of); SGN, 1 rue des Herons Montigny le Bretonneux, 78182 St Quentin Yvelines Cedex (France). Funding organisation: (United States)2002
Nuclear Environment Technology Institute Korea Hydro and Nuclear Power Company, Ltd. P.O.Box 149, Yusung, Taejon 305-600 (Korea, Republic of); SGN, 1 rue des Herons Montigny le Bretonneux, 78182 St Quentin Yvelines Cedex (France). Funding organisation: (United States)2002
AbstractAbstract
[en] Korea is under preparation of its first commercial vitrification plant to handle LLW from her Nuclear Power Plants (NPPs). The waste streams include three categories: combustible Dry Active Wastes (DAW), borate concentrates, and spent resin. The combustible DAW in this research contains vinyl bag, paper, and protective cloth and rubber shoe. The loaded resin was used to simulate spent resin from NPPs. As a part of this project, Nuclear Environment Technology Institute (NETEC) has tested an operation mode utilizing its pilot-scale plant and the mixed waste surrogates of resin and DAW. It has also proved, with continuous operation for more than 100 hours, the consistency and operability of the plant including cold crucible melter and its off-gas treatment equipment. Resin and combustible DAW were simultaneously fed into the glass bath with periodic addition of various glass frits as additives, so that it achieved a volume reduction factor larger than 70. By adding various glass frits, this paper discusses about maintaining the viscosity and electrical conductivity of glass bath within their operable ranges, but not about obtaining a durable glass product. The operating mode starts with a batch of glass where a titanium ring is buried. When the induced power ignites the ring, the joule heat melts the surrounding glass frit along with the oxidation heat of titanium. As soon as the molten bath is prepared, in the first stage of the mode, the wastes consisting of loaded resin and combustible DAW are fed with no or minimum addition of glass frits. Then, in the second stage, the bath composition is kept as constant as possible. This operation was successful in terms of maintaining the glass bath under operable condition and produced homogeneous glass. This operation mode could be adapted in commercial stage
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26 Feb 2002; 7 p; WM Symposia Inc., Tucson, Arizona; Waste Management 2002 Symposium; Tucson, AZ (United States); 24-28 Feb 2002; Available from PURL: https://www.osti.gov/servlets/purl/828332-1gsMKP/native/
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Miscellaneous
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BORON COMPOUNDS, CHEMICAL REACTIONS, ELASTOMERS, ELECTRICAL PROPERTIES, ELEMENTS, MANAGEMENT, MATERIALS, METALS, NUCLEAR FACILITIES, ORGANIC COMPOUNDS, ORGANIC POLYMERS, OXYGEN COMPOUNDS, PETROCHEMICALS, PETROLEUM PRODUCTS, PHYSICAL PROPERTIES, POLYMERS, POWER PLANTS, RADIOACTIVE MATERIALS, RADIOACTIVE WASTES, THERMAL POWER PLANTS, TRANSITION ELEMENTS, WASTE MANAGEMENT, WASTES
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AbstractAbstract
[en] The current small break loss of coolant accident (SBLOCA) mass and energy (M/E) release analysis methodology for the pressurized water reactor (PWR) was developed based on the evaluation method of the emergency core cooling system. The method is somewhat deterministic and includes conservative modeling assumptions. KOPEC has developed a new M and E release calculation methodology, KIMERA including SB-LOCA methodology to model the containment response more realistically. This paper demonstrates a new methodology for SBLOCA M/E release analysis and provides the results for Ulchin nuclear power plant units 3 and 4 (UCN 3 and 4). Also, the results are compared with UCN 3 and 4 FSAR. The more realistic M/E release data are generated for the containment design and environmental qualification of equipment
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Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2008; [2 p.]; 2008 autumn meeting of the KNS; Pyongchang (Korea, Republic of); 30-31 Oct 2008; Available from KNS, Daejeon (KR); 2 refs, 4 figs, 2 tabs
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AbstractAbstract
[en] Thromboangiitis obliterans is now concepted as a clinical entity with unknown etiology and pathogenesis, occurring in young adult male smoker. Peripheral arteriography is important for decision of biopsy site and vascular bypass graft whom thromboangiitis obliterans is suspected. At Department Of Radiology, Seoul National University Hospital, 53 patients of thromboangiitis obliterans, were studied with peripheral arteriography during August 1971 to January 1979. The arteriography findings are acute and segmental occlusion and diffuse narrowing. The most frequent occlusion sites are anterior tibial artery and posterior tibial artery, and 23 patients the occlusion was above popliteal artery. Proximal cork-screw type collaterals are developed in large arterial occlusion and distal tree-root appearance in small arterial occlusion below popliteal artery. Standing waves are seen in 17 arteries of 12 patients, and most frequent (7 arteries) in superficial femoral arteries.
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17 refs, 5 figs, 4 tabs
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Journal Article
Journal
Journal of the Korean Radiological Society; ISSN 1738-2637; ; v. 15(1); p. 95-100
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Kim, C. W.; Kum, O. H.; Park, J. H.; Lee, S. H.; Ryu, Y. H.
Proceedings of the KNS-KARP Joint spring meeting2002
Proceedings of the KNS-KARP Joint spring meeting2002
AbstractAbstract
[en] MOST (Ministry of Science and Technology) asked the KINS (Korea Institute of Nuclear Safety) to develop the safety review guidelines related to the severe accident policy and the severe accident management in accordance with the 'severe accident policy statement; MOST, 2001. 8.30). On the other hand, the licensee of nuclear power plant has the planning to establish the severe accident management programs for the individual plant by the year 2008 and Table 1 represents detailed schedule of these plan. The purpose of safety review guideline(SRG) of severe accident management program (SAMP) is to develop a guideline which will be used to review the validity of the licensee's SAMP. To accomplish above purpose, technical review performs for the foreign countries of their SAMP status and develop a 'Safety Review Guideline (SRG) of Severe Accident Management Program' which is suitable for Korean Plants. Application results this SRG to the SAMP of YGN 5,6 are generally acceptable. KINS will improve this SRG after comments from the domestic nuclear industry during 2002 and fix it as the KIN's SRG 19.3 (Severe Accident Management Program). It will be used to review the SAMP of operational and newly constructed plants in Korea
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Korean Nuclear Society, Taejon (Korea, Republic of); Korean Association for Radiation Protection, Seoul (Korea, Republic of); [CD-ROM]; May 2002; [11 p.]; 2002 joint spring meeting of the KNS-KARP; Gwangju (Korea, Republic of); 23-24 May 2002; Available from KNS, Taejon (KR); 8 refs, 2 tabs
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Choi, J. R.; You, B. S.; Kim, C. W.; Park, J. G.; Ha, J. H.
Proceedings of the Korean Radioactive Waste Society Fall, 20032003
Proceedings of the Korean Radioactive Waste Society Fall, 20032003
AbstractAbstract
[en] 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 concretes, 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
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Source
Korea Radioactive Waste Society, Taejon (Korea, Republic of); 724 p; 2003; p. 48-53; 2003 Fall Meeting of the Korean Radioactive Waste Society; Cheju (Korea, Republic of); 27-29 Nov 2003; Available from the Korean Radioactive Waste Society, Taejon (Korea, Republic of); 5 figs, 2 tabs
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Miscellaneous
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Park, M. S.; Kim, C. W.; Choi, C. J.; Lee, S. Y.; Seo, J. T.
Proceedings of the Korean Nuclear Society spring meeting1999
Proceedings of the Korean Nuclear Society spring meeting1999
AbstractAbstract
[en] In accordance with adoption of POSRV, as a safety valve to protect overpressure of reactor coolant system for KNGR, the sensitivity study were performed to determine the actuation setpoint of POSRV. The results of the sensitivity studies for the loss of condenser vacuum and the inadvertant opening of POSRV were described in this paper. Various actuation setpoint of POSRV were assumed for sensitivity study in conjunction with initial conditions, that is, the core inlet temperature, reactor coolant flow, pressurizer pressure and level, and steam generator water mass. The actuation setpoint of POSRV was determined so that the results of these sensitivity studies under the most conservative conditions could meet the acceptance criteria (below 110% of design pressure and above the specified acceptable fuel design limit) and it was verfied that the design of POSRV was pertinent to KNGR
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KAERI, Taejon (Korea, Republic of); [one CD-ROM]; May 1999; [11 p.]; 1999 spring meeting of the Korean Nuclear Society; Pohang (Korea, Republic of); 28-29 May 1999; Available from KNS, Taejon (KR); 5 refs, 6 figs, 6 tabs
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Miscellaneous
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AbstractAbstract
[en] This paper presents experimental results which explore the capability of a CW laser speckle photography for tile measurement of in-plane displacement at high temperature. The serious restrictions on the application of the method seem to be the ambient air turbulence and the change of surface texture caused by the oxidation, as they tend to decorrelate the double exposured speckle patterns. In order to assess only the effect of air turbulence, a ceramics-coated stainless steel plate is heated in air and Ar-laser speckle grams are made with combination of temperature and lateral translation displacement. The slight reduction in visibility of Young's fringes is observed at 1000 .deg. C. The analyses of Young's fringes are carried out by a image processing system using a TV-camera and computers, and the result agrees well with the micrometer reading. Furthermore, uncoated stainless steel and Hastelloy X plates are tested and the effect of oxidation is also evaluated. The experimental results demonstrate that a CW laser speckle photography is applicable at temperatures up to 1000 .deg. C.
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6 refs, 12 figs, 5 tabs
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Journal Article
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Journal of the Korean Society for Nondestructive Testing; ISSN 1225-7842; ; v. 10(1); p. 47-55
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