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Session 60-61 Abstracts <strong>The</strong>se four framework areas were competed through an Official Journal of European Union (OJEU) process in 2008. Although all four areas involve waste management, Waste Processing and Material Characterisation specifically deal with Higher Activity Waste (HAW) waste management issues. <strong>The</strong> Waste Processing area was awarded to three groups: (i) National Nuclear Laboratory (NNL), (ii) Consortium led by Hyder Consulting Ltd, and (iii) Consortium led by UKAEA Ltd. <strong>The</strong> Material Characterisation area was awarded to three groups: (i) NNL, (ii) Serco, and (iii) Consortium led by UKAEA Ltd. 5) SIDE RADWASTE TREATMENT FACILITIES FOR THE WESTINGHOUSE AP1000 PROJECTS IN SANMEN UND HAIYANG, PR CHINA - 16410 Andreas Roth, Hansa Projekt Anlagentechnik GmbH (Germany); John Merrell, Westinghouse Electric Co Uk Ltd (UK) Currently two blocks of the Westinghouse AP1000 pressurized water-reactor are built at the sites Sanmen und Haiyang in the Peoples Republic of China. 6-8 blocks of the reactor type will be operated during ultimate installation at each side. <strong>The</strong> waste treatment concept in the US is orientated towards external conditioning service and therefore the Westinghouse plan of concept for the AP1000 doesnt contain any other waste treatment facilities for waste beside the power plants water treatment. Loading units for transport to external service providers are planned instead of that. <strong>The</strong>re is no essential infrastructure of potential service providers in the PR China and therefore a coherent waste treatment concept was needed for the building license. Because of that Hansa Projekt Anlagentechnik GmbH developed a plan of concept for building waste treatment centers at the different sides in cooperation with the Shanghai Nuclear Engineering and Design Institute. 6) STATISTICAL MODELLING APPLIED TO THE CONTENTS OF WASTE DRUMS - 16085 Richard Bull, Ian Pearman, Nuvia Limited (UK) Gamma spectrometry is widely used to determine the radioactive content of waste drums. However, the results of such surveys often result in large numbers of limit-of-detection (LOD) results. In this paper we will show how simple statistical methods can be used to obtain useful information on the average drum activities, even in these unfavourable circumstances. Results from measurements on 60Co, 152Eu, 154Eu activities in drums of waste from decommissioning of the GLEEP reactor suggest that these activities are lognormally distributed with geometric standard deviations (GSD) ranging from 3-4. This statistical model can be used to extract information from 235U, 234mPa and 234Th datasets which show only LOD activity results. In a repository of N drums, each with activity
Abstracts Session 61 According to regulations, a number of design basis cases should be identified based on scenarios that can be shown to be especially important from the standpoint of risk. A few such cases can be derived from the results of SKBs most recent safety assessment SR-Can. <strong>The</strong>se cases also involve several assumptions on the state of other barriers. 2) CHARACTERIZATION OF A FE-BASED ALLOY SYSTEM FOR A AFCI METALLIC WASTEFORM - 16134 Mark Williamson, Savannah River National Lab (USA); Marie Kane, Savannah River National Laboratory (USA); Bob Sindelar, Savannah River National Lab (USA) <strong>The</strong> AFCI waste management program aims to provide a minimum volume stable waste form for high level radioactive waste from the various process streams. <strong>The</strong> AFCI Integrated Waste Management Strategy document has identified a Fe-Zr metallic waste form (MWF) as the baseline alloy for disposal of Tc metal, undissolved solids, and TRUEX fission product wastes. Several candidate alloys have been fabricated using vacuum induction melting to investigate the limits of waste loading as a function of Fe and Zr content. Additional melts have been produced to investigate source material composition. <strong>The</strong>se alloys have been characterized using SEM/EDS and XRD. Phase assemblage and specie partitioning of Re metal (surrogate for Tc) and noble metal FP elements into the phases is reported. 3) THE COLLABORATIVE EU PROJECT RECOSY - 16203 Bernhard Kienzler, Gunnar Buckau, Forschungszentrum Karlsruhe (Germany) <strong>The</strong> Collaborative Project (CP) ReCosy (Redox Controlling Systems) was established in 2008. It falls within the EURATOM program and is implemented within the European Commission’s 7th Framework Program. Main objectives of CP ReCosy are the sound understanding of redox phenomena controlling the long-term release/retention of radionuclides in nuclear waste disposal and providing tools to apply the results to Performance Assessment/Safety Case. Although redox is not a new geochemical problem, different questions are still not resolved and thus raised by implementers and scientists. Radionuclide redox transformations on minerals are considered to be decisive scenarios in various FEP lists. 32 institutions from 13 European countries contribute to the 4-years CP by i) development of advanced analytical tools, ii) investigations of processes responsible for redox control (thermodynamically and kinetically controlled processes, surface reactions and microbial processes), iii) provision of required data on redox controlling processes, and iv) response of the disposal systems to external/internal disturbances. Systems which are investigated comprise simple very well defined ones under controlled laboratory conditions, complex laboratory systems, near-natural systems in the laboratory, real systems, and near-field systems controlled spent nuclear fuel. 4) MODELLING RADIONUCLIDE MOBILITY OF SPENT FUEL IN A DEEP GEOLOGICAL REPOSITORY LOCATED IN A CLAY BEDROCK - 16240 Abel Tamayo, Lara Duro, Jordi Bruno, Amphos 21 (Spain);Aurora Martínez-Esparza, ENRESA (Spain) Source term models are widely used to assess the behaviour of spent nuclear fuel after final disposal. However, most models do not take into account some phenomena which are expected to control the transport of radionuclides through the near field. Some uncertainties arise from this fact, thus making it difficult to obtain proper simulations of radionuclide behaviour in the near field. In this work, we have used a compartmental code to built up an integrated source term model which overcomes the above-mentioned drawbacks. Such model takes into account radiolytically-mediated matrix dissolution, radioactive decay chains, diffusive transport, and retardation by sorption and secondary phase precipitation, among other processes. In addition, this model has been used to estimate radionuclide mobility from spent fuel located in a conceptual clay geological repository. 5) EVALUATION OF MECHANICAL EFFECTS OF THE FAULT MOVEMENT ON THE ENGINEERED BARRIER SYSTEM - 16269 Yuya Saito, Japan Atomic Energy Agency, (Japan); Mayuka Nishimura, Takashi Hirai, Takenaka Civil Engineering & Construction Co., Ltd, (Japan); Kenji Tanai, Morimasa Naito, Japan Atomic Energy Agency (Japan) Experiments and numerical analyses have been conducted to investigate the consequences of an active fault crosscutting the engineered barrier system (EBS) of a high-level radioactive waste (HLW) repository. Experiments were performed using laboratory simulation test equipment at a scale of 1:20, which can simulate the chosen shear displacements of 80 % and 140 % of the buffer thickness, and the chosen shear rates of 0.1 m/s, 0.05 m/s and 0.01 m/s. <strong>The</strong> experiments have so far demonstrated that the metal overpack will be rotated, but not breached, due to the plasticity of the surrounding bentonite buffer. <strong>The</strong> total pressure on the bentonite buffer increases with an increase in the shear rate. 6) STUDY ON PERFORMANCE ASSESSMENT FOR HLW REPOSITORY IN CHINA - 16228 Weiming Chen, Ju Wang, Rui Su, Yunfeng Li, Beijing Research Institute of Uranium Geology (China) This paper presents the latest achievements of performance assessment (PA) for high level radioactive waste (HLW) repository in China. <strong>The</strong> first PA model, taking Beishan granite site as an example, is established with GoldSim and is verified by comparison with Japanese PA model. <strong>The</strong>n the behaviors of granite repository in Beishan area are simulated. <strong>The</strong> results from these simulations show that the engineered barrier is the most important part inside the repository, especially its bentonite plays a key role in the retardation of repository after the nuclide is released from the vitrified waste. Five sensitive parameters are identified and two design parameters are optimized. As a result, it has been proved that performance assessment model is a necessary tool to understand the behaviors of repository, to identify sensitive parameters, and to optimize design parameters. 135
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FINAL PROGRAM ICEM’09/ DECOM’09
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Table of Contents ICEM’09/DECOM
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Transportation by Ferry to Liverpoo
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Conference Registr
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gram to provide guidance on selecti
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Notes 9
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Liverpool City Center Map Bus Loadi
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Condensed Conference</stron
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SESSION # Technical Program at a Gl
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Technical Sessions Monday PM SESSIO
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Technical Sessions Tuesday AM SESSI
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Technical Sessions Tuesday AM 2. Ri
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Technical Sessions Tuesday PM Seide
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Technical Sessions Wednesday AM Wed
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Technical Sessions Wednesday AM SES
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Technical Sessions Wednesday PM 4.
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Technical Sessions Thursday AM SESS
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Exhibitors Listings We would like t
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ATKINS STAND: 32 Contact: Nigel Tho
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emote operations. Our background of
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GOLDSIM STAND: 58 TECHNOLOGY GROUP
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JFIMS & JFN STAND: 67 Contact: JFIM
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ased system. Our professional staff
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assembled a team whose guiding prin
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demanding clients, and we also offe
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management, and technical consultan
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WORLEYPARSONS STAND: 56/57 Contact:
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Abstracts Session 4 The</st
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Abstracts Session 5-6 ically made o
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Abstracts Session 7-8 Brief descrip
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Abstracts Session 9 3) SHARED, REGI
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Abstracts Session 10-12 The
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Abstracts Session 12 joint awarenes
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Abstracts Session 15 SESSION 15 - D
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Abstracts Session 16 2) STRATEGIC P
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Abstracts Session 17 3) DESIGN OF P
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Abstracts Session 18 After the eval
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Abstracts Session 19 SESSION 19 - G
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Abstracts Session 22 SESSION 22 - P
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Page 91 and 92: Abstracts Session 27 conditions pre
Page 93 and 94: Abstracts Session 28 posal of spent
Page 95 and 96: Abstracts Session 28-29 The
Page 99 and 100: Abstracts Session 31 5) INTERDIGITA
Page 101 and 102: Abstracts Session 33 SESSION 33 - D
Page 103 and 104: Abstracts Session 34 D) FURTHER DEV
Page 105 and 106: Abstracts Session 34-36 TcO2(s). Fo
Page 107 and 108: Abstracts Session 36 4) PRELIMINARY
Page 109 and 110: Abstracts Session 37 4) ENVIRONMENT
Page 111 and 112: Abstracts Session 38 3) HYDROGEOLOG
Page 115 and 116: Abstracts Session 41 mined in an an
Page 117 and 118: Abstracts Session 43 radioactivity
Page 119 and 120: Abstracts Session 45 testing and op
Page 121 and 122: Abstracts Session 48 As a result of
Page 123 and 124: Abstracts Session 49-50 A novel met
Page 125 and 126: Abstracts Session 51 ings require m
Page 127 and 128: Abstracts Session 52-54 reflects ev
Page 129 and 130: Abstracts Session 55 It is found th
Page 131 and 132: Abstracts Session 56-57 2) A TRULY
Page 133 and 134: Abstracts Session 58 2) A SUCCESSFU
Page 135: Abstracts Session 59-60 4) SAFETY E
Page 139 and 140: Abstracts Session 62-63 4) BIOAVAIL
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