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Abstracts inert atmosphere, etc.) have been adequately addressed. An approach to those work formations is to analyze mechanical characteristics of structural components which are the mechanical properties of grid spring reflecting its irradiation effect, SNF strength and SNF structural deformation such as its bow, twist etc. Those informations are also used to evaluate hypothetical accident like a drop accident of SNF cask/canister, to select limiting fuel assembly for cask/canister to accommodate various kinds of SNFs and to design transportation or storage system for SNFs. Especially, the fuel assembly structural properties are a sort of essential data. Thus, in this paper, some approaches to evaluate SNF mechanical characteristics are suggested through the existing technical information review, some test data and the analysis methodology, and also closely study the mechanical characteristics of a representative SNF for its general comprehension. 23) 40200 – Development of Program Categories to Assess the Radiological Dosage during Spent Fuel Transportation Suhong Lee , Sangwon Shin, Enesys, Jaemin Lee, Enesys.Co.,Ltd. (Korea Rep.); Kiyroul Seong, Jeonghyoun Yoon, KRMC (Korea Rep.) Korea is seeking the plan to put spent fuels in interim storage facility as disposal business of low and intermediate-Level radioactive waste started. First, There is a strong probability that transport of the spent fuels will be arranged in marine transportation. Accordingly, building of transportation risk assessment system in the marine transportation comes to the force as a real problem. Therefore, in this study, I organized the basic categories of program to develop transportation risk assessment program about specialized transport in marine transportation of spent fuels. The possibility of radiation exposure in marine transportation consists of the normal condition and the accident condition. The direct radiation exposure that the workers in loading and crews of the vessels will receive is considered in the normal condition. I decide the leakage rate dividing the accident condition that the radioactive materials are spilled into air and marine and doing the effect by emission by fire and physical damage. Also, as for the radioactive materials floated in the air, calculated applying the atmospheric dispersion factors to them and evaluate the direct radiation exposure and internal radiation exposure. As for marine contamination, the radioactive materials move along ocean currents. Generally, there can be the direct radiation exposure of ocean activists due to the moving radioactive materials according to the flow of the ocean currents in contaminated marine and the direct radiation exposure and the indirect radiation exposure by breathing of the subjects near the shores due to the smoke and fog form that occurs by seawater. Also the internal radiation exposure by intake contains one of marine life. I set the categories to build the overall programs to build this with the comprehensive program that have effects on radiation while the spent fuels are transported combining it with the transport conditions or the characteristics of the subjects of radiation exposure and the environmental factors. And building of the program will be completed through it. The completed program can evaluate various conditions of marine transportation after it will be specialized in marine transportation. 24) 40225 – Exploiting synergies between the UK & Japanese geological disposal programmes Ellie Scourse, Atkins (UK); Hideki Kawamura, Obayashi Corporation (Japan); Ian G. McKinley, McKinley Consulting (Switzerland) The early ‘80s UK programme for deep geological disposal of high-level radioactive waste was advanced and at the stage of characterising potential sites. When this project was put on hold in the mid ‘80s, much expertise in this field was lost. In Japan R&D in the ‘80s resulted in major generic safety assessments to demonstrate feasibility in the ‘90s. This led to the establishment of NUMO (Nuclear Waste Management Organization of Japan) and the initiation of siting based on volunteerism. This novel approach required more flexible methodology and tools for site characterisation, repository design and safety assessment. NUMO and supporting R&D organisations in Japan have invested much time and effort preparing for volunteers but, unfortunately, no discussions with potential host communities have yet developed to the point where technical work is initiated. Presently, the UK is moving forward; with the NDA RWMD (Nuclear Decommissioning Agency Radioactive Waste Management Directorate) adopting a NUMO-style volunteering approach and a flexible design catalogue. Communities have already shown interest in volunteering. The situation is thus ideal for collaboration. The paper will expand on the opportunities for the UK and Japan to benefit from an active collaboration and discuss how this can be most efficiently implemented. Key Words: UK, Japan, collaboration 25) 40239 – Realistic Consequence Analysis of River Erosion Scenarios for a HLW epository Kaname Miyahara , Makoto Kawamura, Manabu Inagaki, JAEA (Japan); Ian G. McKinley, McKinley Consulting (Switzerland); Michael J. Apted, Monitor Scientific LLC (USA) Uplift and erosion cannot be precluded in most sites in Japan. As no assessment cut-off times have yet been defined, erosive radionuclide release scenarios must be developed and analyzed, even if these occur far in the future. Obviously, uplift and erosion will cause major disruption of the engineered and natural barriers when the repository nears, and is -102-
Abstracts eventually exposed at, the ground surface. In a previous study, a simple linear uplift process was combined with a more detailed assessment of river erosion, which was identified as the key erosion process in Japan. This indicated the robustness of the reference HLW disposal system: the consequences of erosion of the repository being small when compared to the yardstick provided by natural radionuclide fluxes. The original model was rather simple, but highlighted the importance of cyclic erosion in response to the changing environment in glacial and inter-glacial periods. Therefore, the geological record of such cycles preserved in Japan as river terraces has been studied further, with the aim of constructing a more realistic river erosion model. It is evident that, although riverbed deepening occurs during glacial cycles, significant sedimentation also occurs and the timing of these phases during the cycle differs in the upper and lower reaches of rivers. Unfortunately the situation is particularly complicated in mid-reach settings – and these may be most relevant for repositories that avoid mountain locations and cannot be established in the highly populated coastal plains. Here interpretation of complex river terrace structures must take into account both variations in the length of past glacial/inter-glacial periods and in the resistance of different riverbeds to erosion. Further, when the width of river channel is significantly less than that of the valley, meanders develop giving sequences of river terraces that are observed only on one side (asymmetric) or on both sides (symmetric) of river. Unlike in the upper reaches, in such environments it cannot be assumed that valley profiles are effectively constant in time and the gradual progress from eroding mountains towards formation of a peneplain has to be considered. This paper describes a conceptual model based on generalization of these observations and resultant consequence analyses, again using comparisons with natural radionuclide fluxes. Geological evidence supporting such erosion models will be discussed in another paper presented in ICEM’10 by Kawamura et al. 26) 40272 – Removal of Fission Products in the Spent Electrolyte Using Iron Phosphate Glass as a Sorbent Ippei Amamoto, Masami Nakada, Yoshihiro Okamoto, JAEA (Japan); Naoki Mitamura, Tatsuya Tsuzuki, Central Glass Co. Ltd. (Japan); Yasushi Takasaki, Atsushi Shibayama, Akita University (Japan); Tetsuji Yano, Tokyo Institute of Technology (Japan) The [3LiCl(59.5mol%)-2KCl(40.5mol%)] eutectic medium used in the pyroreprocessing by the electrorefining method will be contaminated by the accumulation of various actinoid elements (An) and fission products (FP) due to prolonged electrolytic operation. Though the An can be removed at the pyrocontactor step by extraction using cadmium melt, the FP remain in the eutectic medium, which is regarded as a spent electrolyte at certain stage, can cause the rising of the melting point of the electrolytic bath and /or lowering the current efficiency. Some measures e.g., its replacement by a virgin medium, etc. should be taken to maintain its stable condition. The constant replacement of the electrolyte, however, could lead to the generation of enormous volume of high-level radioactive waste (HLW). In terms of environmental load reduction and economical improvement, it is desirable to have the spent electrolyte purified for recycling by removing its FP. Some technical developments on spent electrolyte treatments have been carried out in several countries. One of them is the zeolite sorption of FP following An removal which is being developed in the USA, Japan, etc.. Meanwhile, the contaminants precipitation methods by converting contaminants to insoluble compounds are undertaken in Russia and a few other countries and are anticipated to reduce the total volume of HLW. In the case of the Russian process, its purpose is to remove contaminants such as the minor actinoids (MA) and rare earth elements (REE) from the medium before its disposal. In our case, the main objective is to recycle the purified medium, delaying its disposal for as long as possible. It is with this objective in mind that this study was undertaken. We have introduced the simple filtration method to remove REE particles which were formed due to the conversion of REE chlorides to phosphates. Here, the iron phosphate glass is used as a filtration medium for the removal of FP particles. However, some soluble FP such as compounds of alkali-metals, alkaline-earth metals, etc. still remain in the eutectic medium. This time around, on an experimental basis, the iron phosphate glass has been used as a sorbent instead, to remove the soluble FP. We have obtained some positive results and have intention to incorporate it into the spent electrolyte recycle process as a part of the FP separation and immobilization system. 27) 40295 – Propagation and Interactions of Acoustic Waves in a Waveguide Attached at the Surface of Rock Jin-Seop Kim, Kyung-Soo Lee, S. Kwon, KAERI (Korea Rep.); Gye-Chun Cho, KAIST (Korea Rep.) The dynamic response of a rock mass is inevitable in the systematic long-term monitoring and management in the radioactive waste disposal repository. With this point of view, AE (acoustic emission) detection is considered to be a promising technique for monitoring the in-situ performance of near-field rock mass. In this study, propagation and interactions of guided acoustic waves in a waveguide, which is required to in-situ application of AE monitoring system were investigated. The changes in acoustic wave amplitude, time delay, frequency variation, and system transfer function were measured between the waveguide and a rock sample. Subsequently the waveguide coupling conditions filled with epoxy were compared with mechanical type of coupling for the validity of field application. Three type of coupling methods were used to compare each other. One is a type of direct contact with granite specimen(Ch.2) which is same kind of rock mass with KURT(Korea Underground Research Tunnel) by using a vacuum grease as a reference data. Another is a waveguide-aided connection method without any coupling fluid(Ch.1) and the other is a same type with Ch.1 except for the use of epoxy resin for a coupling fluid between the gap of a specimen and a waveguide. The time delay between CH.1 and CH.2 was 0.025 msec and in case of CH.3 and CH.2 0.012 msec. Energy decay ratio of first -103-
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FINAL PROGRAM The 13th Internationa
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General Information Objectives and
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Insurance and Liability All partici
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Map around Conference Venue, Hotels
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ICEM2010 Technical Sessions at a Gl
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ICEM2010 Technical Sessions at a Gl
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SESSION D3: Planning Tuesday 09:00
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Sealed Radioactive Sources (DSRS) R
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Susumu Kawakami, IHI Corporation (J
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Environments of Geological Disposal
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