scholarly journals Current status of Geological disposal by “all-Japan” activities (2)

2022 ◽  
Vol 64 (1) ◽  
pp. 46-50
Author(s):  
Hiromitsu Saegusa ◽  
Toshiyuki Matsuoka ◽  
Masakazu Niwa ◽  
Eiji Sasao ◽  
Akira Hayano
Author(s):  
Kazumi Kitayama

The programme for disposal of radioactive waste in Japan is now moving ahead on a number of fronts. On the regulatory side, responsibility for TRU waste disposal has been assigned to NUMO and guidelines for the safety goals for disposal of LLW have been published. NUMO, as the implementer for the deep geological disposal programme, has been developing the special tools for project management that are needed as a result of the decision to adopt a volunteering approach to siting. NUMO is also building up the technical infrastructure for flexible tailoring of site characterisation, repository design and the associated safety assessment to the conditions found in any volunteer site. This work requires openness and transparency in decision-making but, as several sites may need to be investigated in parallel, particular emphasis is placed on operational practicality.


2013 ◽  
Vol 361-363 ◽  
pp. 912-916
Author(s):  
Ke Man ◽  
Xiao Li Liu ◽  
Ju Wang ◽  
Rui Su ◽  
Yong Qiang Zhu

Based on the diagenesis, classification and its physical, mechanical, and hydromechanical properties of fractured rock, this paper describes the current status of the fractured rock seepage models and their characteristics. Especially from the point of the safety assessment of the geological disposal of the high level radioactive waste, the discrete fracture network model, the equilibrium continuous medium model and the double media continuous model have been elaborated, and has been analyzed and compared with each other. Furthermore, the double fracture systems for rock flow have been introduced as the much better suitable seepage model for the geological disposal of the high level radioactive waste. In the double fracture systems seepage model, the seepage flow is described and reflected by the main fracture system, and the water store property is given by the subordinate fracture system. The appropriate seepage model for the geological disposal of the high level radioactive waste can be achieved through the double fracture systems, combined with the hydrological testing data in site and other geological information.


2015 ◽  
Vol 79 (6) ◽  
pp. 1581-1589 ◽  
Author(s):  
Povilas Poskas ◽  
Asta Narkuniene ◽  
Dalia Grigaliuniene

AbstractIn Lithuania all the spent nuclear fuel (SNF) came from operation of the Ignalina nuclear power plant with two reactors of RBMK type (RBMK is a Russian acronym for 'Channelized Large Power Reactor' which is a water-cooled graphite-moderated reactor: RBMK-1500). Approximately 22,000 SNF assemblies are due for geological disposal in Lithuania. Currently it is envisaged that SNF will be stored in dry interim storage facilities (new and existing) for at least 50 y prior to possible deep geological disposal.The decision on the final SNF management option (disposal in a national repository, disposal in regional repositories, etc.) has not yet been made but some investigations of the possibilities to dispose of the SNF in Lithuania have been initiated. With the support of Swedish experts, analysis of possible geological formations for SNF disposal was performed and the existence of potentially suitable formations agreed. The geological formations prioritized as prospective include the crystalline rocks in southern Lithuania and two clayey formations: the Lower Triassic clay formation and the Lower Cambrian Baltic Group clay formation, with priority given to the Lower Triassic clay formation.This paper presents the main aspects of the research and other activities undertaken over the past decade in the field of SNF disposal: international cooperation; current status and plans for the Lithuanian national program; further investigations required; and competence developments.


Author(s):  
Hiroyoshi Ueda ◽  
Katsuhiko Ishiguro ◽  
Kazumi Kitayama ◽  
Kiyoshi Oyamada ◽  
Shoko Sato

NUMO (Nuclear Waste Management Organization of Japan) has a responsibility for implementing geological disposal of vitrified HLW (High-Level radioactive Waste) in the Japanese nuclear waste management programme. Its staged siting procedure was initiated in 2002 by an open call for volunteer sites. Careful management strategy and methodology for the technical decision-making at every milestone are required to prepare for the volunteer site application and the site investigation stages after that. The formal Requirement Management System (RMS) is planned to support the computerized implementation of the specific management methodology, termed the NUMO Structured Approach (NSA). This planned RMS will help for comprehensive management of the decision-making processes in the geological disposal project, change management towards the anticipated project deviations, efficient project driving such as well-programmed R&D etc. and structured record-keeping regarding the past decisions, which leads to soundness of the project in terms of the long-term continuity. The system should have handling/management functions for the database including the decisions/requirements in the project in consideration, their associated information and the structures composed of them in every decision-making process. The information relating to the premises, boundary conditions and time plan of the project should also be prepared in the system. Effective user interface and efficient operation on the in-house network are necessary. As a living system for the long-term formal use, flexibility to updating is indispensable. In advance of the formal system development, two-year activity to develop the preliminary RMS was already started. The purpose of this preliminary system is to template the decision/requirement structure, prototype the decision making management and thus show the feasibility of the innovative RMS. The paper describes the current status of the development, focusing on the initial stage including work analysis/modeling and the system conceptualization.


Author(s):  
P. Marjatta Palmu ◽  
Torsten L. Eng

Several European waste management organizations have started the work on creating a technology platform to accelerate the implementation of deep geological disposal of radioactive waste in Europe. There is an increasing consensus in the international community [1] about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste, and other long-lived radioactive wastes. At the same time, the European citizens [2] have a widespread wish for a solution for high-level radioactive waste disposal. A majority of the European countries with nuclear power have active waste management programmes, but the current status and the main challenges of those programmes vary. The most advanced waste management programmes in Europe (i.e. Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a joint awareness that cooperation on the scientific, technical, and social challenges related to geological disposal is needed, and the cooperation will be beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. Several decades of research, development and demonstration (RD&D) have been carried out in the field of geological disposal. International opportunities of cooperation and establishing a technology platform were explored in the European Commission co-funded projects like Net.Excel [3] and CARD [4]. According to the CARD project, the majority of the funding for RD&D in waste management comes from the implementing organizations. It is envisaged that a technology platform would enhance European cooperation in this area. The platform intends to constitute a tool for reducing overlapping work, to produce savings in total costs of research and implementation, and to make better use of existing competence and research infrastructures. After the final workshop of the CARD project in 2008, SKB (Sweden) and Posiva (Finland) were committed to lead the preparation work to set-up the Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP). Other implementers from France, Germany, Switzerland, Great Britain, Spain, and Belgium joined en suite. A Vision Document for the IGD-TP is about to be finalized after a wider consultation was carried out in July 2009. The final Vision Document and the platform are launched during November 2009. Simultaneously, the preparation of the Strategic Research Agenda for the technology platform’s joint work starts.


2012 ◽  
Vol 76 (8) ◽  
pp. 3439-3444 ◽  
Author(s):  
M. Palmu ◽  
T. Eng ◽  
T. M. Beattie

AbstractSeveral European waste management organizations have started work on creating a technology platform to accelerate the implementation of deep geological disposal of radioactive waste in Europe. There is an increasing consensus in the international community about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste and other longlived radioactive wastes. At the same time, European citizens have a widespread desire for a permanent solution for high-level radioactive waste disposal. A majority of European countries with nuclear power have active waste-management programmes, but the current status and the main challenges of those programmes vary. The most advanced waste management programmes in Europe (i.e. those in Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a joint awareness that cooperation on the scientific, technical and social challenges related to geological disposal is needed, and that it is beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. It is envisaged that a technology platform would enhance European cooperation in this area. The platform will provide a tool for reducing overlapping work, to produce savings in total costs of research and implementation, and to make better use of existing competence and research infrastructures. From 2008, SKB (Sweden) and Posiva (Finland) led the preparation work to set up the implementing geological disposal of radioactive waste technology platform (IGD-TP). Since then other implementers from France, Germany, Switzerland, United Kingdom, Spain and Belgium have joined the project. To date a strategic research agenda for the platform has been prepared and consulted upon, which is now the basis for taking the platform into a deployment phase.


2021 ◽  
Vol 1 ◽  
pp. 129-130
Author(s):  
Axel Liebscher ◽  
Heini Reijonen ◽  
Ismo Aaltonen ◽  
Christina Lilja ◽  
Simon Norris ◽  
...  

Abstract. One of the key requirements for the deep geological disposal of high-level nuclear waste is the assessment of its long-term performance and safety (up to 1 Ma). Regarding engineered barrier system materials, such as copper, much of the data available comes from short-term investigations, such as laboratory experiments at different scales. Copper is an important part of many waste packaging and disposal concepts, e.g. KBS-3 developed in Sweden and Finland and Mark II developed in Canada. Natural analogues provide another important way of obtaining understanding on potential repository system behavior. Observations made from the geological systems can be utilized in the safety case, providing information on the assessment time scale. Copper analogue studies (both natural analogues and archaeological analogues) have been reported in the literature and they have been extensively reviewed by various authors (e.g. Miller et al., 2000) and by safety case projects (e.g. Reijonen et al., 2015) within waste management organizations. So far, only a few studies have focussed on the general stability of native copper within its natural media (e.g. Milodowski et al., 2000; Marcos, 2002). Keweenaw native copper occurrences (Lake Superior, USA) have been mentioned as a qualitative source of information (e.g. in Miller et al., 2000); however, data to be used in process-based safety assessments for geological disposal are lacking. These deposits have been mined for a long time and there is a great deal of knowledge related to them as well as samples collected, but no formal review has been made from the geological disposal point of view. The native copper at the Keweenaw area reflects various geological environments from bedrock to sediment and even anthropogenic mine site remnants and geochemical environments (e.g., anoxic vs. oxic, sulphur-free vs. sulphur-bearing). It thus provides a unique complementary data source that will be useful for estimating processes governing behavior of metallic copper. The MICA project phase I systematically collects and reviews the existing literature and data on the Michigan copper analogue sites and available sampling potential. Here, we present the current status of the project.


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