scholarly journals Performance based regulatory requirements for radioactive waste and waste acceptance criteria

2020 ◽  
Vol 27 (2) ◽  
pp. 94-103
Author(s):  
Hiroomi AOKI ◽  
Ryo INOUE ◽  
Satoru KAWASAKI
2014 ◽  
Vol 1665 ◽  
pp. 3-12 ◽  
Author(s):  
Michael I. Ojovan ◽  
Anthony J. Wickham

ABSTRACTAn overview is given of an International Atomic Energy Agency Coordinated Research Project (CRP) on the treatment of irradiated graphite (i-graphite) to meet acceptance criteria for waste disposal. Graphite is a unique radioactive waste stream, with some quarter-million metric tons worldwide eventually needing to be disposed of. The CRP has involved 24 organizations from 10 Member States. Innovative and conventional methods for i-graphite characterization, retrieval, treatment and conditioning technologies have been explored in the course of this work, and offer a range of options for competent authorities in individual Member States to deploy according to local requirements and regulatory conditions.


Author(s):  
JooWan Park ◽  
Chang-Lak Kim ◽  
Jin Beak Park ◽  
Eun Yong Lee ◽  
Youn Myoung Lee ◽  
...  

An integrated safety assessment system to be used for evaluation of near-surface disposal concept has been developed within the framework of safety assessment methodology taken for low- and intermediate-level radioactive waste disposal in Korea. It is to provide an evaluation of the safety of the disposal system in a clear, comprehensive and well-documented manner, and to integrate the results into a defensible package showing reasonable assurance of compliance with regulatory requirements for licensing application. This system is made up of two key components, a system-level safety assessment code and an input database/quality assurance module for safety assessment, which both are interfaced with each other.


Author(s):  
M. Sokcic-Kostic ◽  
F. Langer ◽  
R. Schultheis

Low and intermediate level radioactive waste must be sorted and treated before it can be sent to radioactive waste storage. The waste must fulfil an extensive amount of acceptance criteria (WAC) to guarantee a safe storage period. NUKEM Technologies has a broad experience with the building and management of radioactive waste treatment facilities and has developed methods and equipment to produce the waste packages and to gather all the required information.


Author(s):  
F.-W. Ledebrink ◽  
P. Faber

Abstract In the period since Germany’s experimental final repository ASSE was closed in 1978, around 5000 drums of conditioned plutonium-bearing radioactive waste from mixed-oxide (MOX) fuel fabrication have accumulated in the interim storage facilities of Siemens AG’s MOX fuel fabrication plant in Hanau, Germany — formerly ALKEM GmbH, now Siemens Decommissioning Projects (Siemens DP). Another 5000 drums will arise in the course of decommissioning and dismantling the MOX plant which has now been underway for some months. Hopes that a final waste repository would soon be able to go into operation in Germany have remained unfulfilled over the last 20 years. Also, the agreements reached between Germany’s electric utilities and the Federal Government regarding the future of nuclear energy have not led to any further progress in connection with the issue of radwaste disposal. A concrete date for a final repository to start operation has still not been set. The German Federal Government estimates that a geologic repository will not be needed for at least another 30 years. Since the opening of a final storage facility is not foreseeable in the near term, Siemens is taking the necessary steps to enable radwaste to be safely stored in aboveground interim storage facilities for a prolonged period of time. Conditioning of radwaste from MOX fuel fabrication by cementing it in drums was started in 1984 in the belief — which was justified at that time — that final storage at the Konrad mine would be possible as of 1995. The quality requirements specified for the waste drums were therefore based on the Konrad acceptance criteria. The operating license for the storage facilities at Hanau at which these drums are presently in interim storage is limited to 20 years and will be expiring in 2004. The drums have not suffered any corrosion to date and, according to past experience, are not expected to do so in the future. However, permission to keep the drums in interim storage for a longer period of time in their current form would be extremely difficult to obtain as their corrosion resistance would have to be demonstrated for a further 30 years. The present goal is therefore to create a waste form suitable for interim storage which needs no maintenance over a long-term period, incorporates state-of-the-art technology and will probably not require any further treatment of the waste packages prior to emplacement in a final storage facility. At the same time, the highest possible degree of safety must be assured for the time during which the waste remains in interim storage. This goal can be attained by conditioning the drums such that they satisfy the requirements currently specified for final storage at the Konrad repository (1). In practice, this means immobilizing the cemented waste drums in concrete inside steel “Konrad Containers” (KCs). The KCs themselves and the concrete backfill represent two further barriers which not only serve as radiation shielding but also protect the drums against corrosion as well as any possible release of radioactive materials in the event of accidents occurring during interim storage. As the KCs are cuboid in shape, they can be stacked in space-saving configurations and are thus particularly suitable for interim storage. Also, due to their extremely heavy weight, theft of the waste packages can be practically ruled out. Despite the fact that the agreements with the German Federal Government have failed to bring opening of the Konrad repository within reach, it is nevertheless a good idea today to condition radwaste in a manner that renders it suitable for ultimate storage there. The agreements between the Government and the utilities are expected at least to result in a land use permit being issued for the Konrad mine before the end of 2001. At present there are no facts known that could cause the safety of this facility to be questioned. Only recently, Germany’s International Nuclear Technology Commission (ILK) confirmed Konrad’s suitability and demanded that it be placed in operation without further delay (2). Even if its operation should, in fact, be blocked by political lobbies, potential legal action or economic considerations, the alternative repository at Gorleben could possibly become operable in approximately 30 years’ time. Gorleben was planned right from the start to be able to accommodate waste packages based on the Konrad acceptance criteria. This means that any waste packages designed for storage at Konrad could likewise be handled and stored at Gorleben. The processes used by Siemens for conditioning of radwaste conform to the recommendations of the “Guidelines for the Control of radioactive Waste with negligible Heat Generation” issued by the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) in 1989 (3).


2021 ◽  
Vol 15 (2) ◽  
pp. 49-62
Author(s):  
E. V. Kuzmin ◽  
◽  
A. V. Kalakutsky ◽  
A. A. Morozov ◽  
◽  
...  

This paper presents the key parameters associated with the disposal method used to dispose of radioactive waste (RW) of Class 2 and 3 in abandoned underground mines of PIMCU site assuming additional isolation of RW containers, adjustment of bedrock geomechanical properties and compliance with regulatory requirements. The paper briefly analyzes international practices focused on RW disposal in natural and artificial underground cavities. It provides a comparison between the forecasted volumes of RW generation at the enterprises of the State Corporation Rosatom and the available underground disposal capacity at PIMCU site. It presents the main characteristics of a paste filling manufactured based on materials from uranium ore processing and used as an insulating filler inside the vaults. The paper summarizes the results of operations on rock mass reinforcement based on an injection method. It indicates the key advantages of the proposed method.


Author(s):  
Gaetano Ruggeri ◽  
Luigi Brusa

Abstract Scope of the paper is to summarise the experience about management of materials arising from decommissioning of Italian NPPs, and to illustrate criteria, procedures and systems, which Sogin is defining to manage the problem of the clearance of sites and materials, considering the international experience and boundary conditions existing in the Country. Since 1962 Enel (the largest Italian utility for electric power) has operated the four Italian nuclear power plants: Garigliano (160 MWe BWR), Latina (210 MWe GCR), Trino (270 MWe PWR) and Caorso (882 MWe BWR). These NPPs were shutdown in the 80’s: Garigliano NPP was shutdown in 1982 following a decision made by Enel, based on technical and economical reasons, Latina, Trino and Caorso NPPs following decisions made by the Italian Government after the Chernobyl accident. The “deferred decommissioning (SAFSTOR)” was the decommissioning strategy selected by Enel and approved by the competent Authorities, due to the lack of a repository for the disposal of radioactive materials and of release limits for clearance of materials. Activities have been started aimed at reaching the “Safe Enclosure” condition, which would have lasted for some decades, before final dismantling of plants. In 1999 the liberalisation of the Italian electricity market led Enel to separate its nuclear activities, forming a new Company, named Sogin, to which decommissioning Italian NPPs was committed. At the same time, considering pressures, both at national and local level, to adopt the “prompt decommissioning (DECON)” strategy, in December 1999 the Italian Minister of Industry, with the intent to accelerate the dismantling of Italian NPPs, presented the plans to create a national repository for nuclear waste, and asked Sogin to revise the decommissioning plans, according to the new global strategy, taking into account all the relevant technical, organisational, financial and legislative aspects of the problem. As the DECON strategy enhances the importance of “clean-up” both of sites and materials, the related aspects are held in due consideration in developing the decommissioning plans, which deal with the following: • characterisation of plant systems, components and structures; • decontamination and dismantling techniques; • monitoring of dismantled materials for clearance; • treatment of dismantled, radioactive materials (which cannot be cleared), prior to disposal; • treatment and conditioning of radioactive waste, prior to disposal; • final clearance of sites. Authorisation requirement related to the release, recycle and reuse of materials produced during plant decommissioning, together with the acceptance criteria for disposal of radioactive materials, are of key importance, considering that the change in decommissioning strategy increases the quantity of radioactive waste to be disposed of, the costs for waste treatment, transportation and disposal, and the capacity of the national repository. In this connection, Sogin is discussing with competent Authorities and Bodies in order to define clearance criteria and disposal acceptance criteria, which neither impair nor complicate the future dismantling operations. In (1) details are given about Italian decommissioning Regulation, decommissioning strategy and Organisation, in order to show the boundary conditions, which exist in Italy for planning and development of NPPs Decommissioning Projects. In the following paragraphs the decommissioning strategy is summarised first together with some critical items of decommissioning; then the Italian regulation about the management of radioactive waste is reported. The management of waste and materials, which will arise from the decommissioning of Italian nuclear power plants, is driven by the requirements imposed by the competent Authorities basing on this regulation.


Author(s):  
Gheorghe Barariu

Most of the radioactive wastes generated in Romania, are due to nuclear activities related to power generation at Cernavoda Nuclear Power Plant NPP Unit 1 and Unit 2. It is provided to construct 2 new Units, in the next period. In Romania, the Nuclear Agency & Radioactive Waste - AN&DR, has established the strategy on low and intermediate level waste disposal and has as objective the commissioning of Final Repository for Low and Intermediate Level Waste – DFDSMA, until 2019. This facility, is in the responsibility of AN&DR. On the other hand, wastes arising from Cernavoda NPP must be treated, in order to achieve the acceptance criteria of DFDSMA. Corresponding Radioactive Waste Treatment Plant - RWTP is in the responsibility of Cernavoda NPP. The main requirement for the RWTP is the necessity to achieve the treatment and conditioning of radioactive wastes that arise both, from NPP operation and from future decommissioning activities of the nuclear facilities, such as to comply with the acceptance criteria of DFDSMA. According to existing requirements, it is necessary to elaborate a Decommissioning Plan, in order to obtain the authorization for construction of the new units. The Decommissioning Plan of Cernavoda NPP will imply the development of a Waste Management Plan, based on existing waste treatment technologies. Taking into account that, the radioactive waste management represents about 43%, comparative with decommissioning activities, which represents only about 35% from total budget of decommissioning, of a CANDU 6 NPP Unit, the paper will present the methodology developed, in order to obtain the optimum Waste Management Plan, taking into account the reduction of environmental impact.


2018 ◽  
Vol 149 ◽  
pp. 01056
Author(s):  
S. Labied ◽  
T. El ghailassi ◽  
A. Bouih ◽  
L. Moutei ◽  
Y. Benbrahim ◽  
...  

Radioactive waste arising as a result of nuclear activities should be safely managed from its generation to final disposal in an appropriate conditioned form to reduce the risk of radiation exposure of technical personnel and of the public and to limit contamination of the environment. The immobilization of low and intermediate level radioactive wastes in cementitious matrices is the most commonly used technique to produce inexpensive waste matrix that complies with regulatory requirements in order to protect humans and the environment against nuisance caused by ionizing radiation. Cement based materials are used in radioactive waste management to produce stable waste forms. This matrix constitutes the first build engineering barrier in disposal facilities. In this work, the kaolin is used to enhance the mechanical performance of the matrix of confinement of ion exchange resins by gradually replacing the sand in mortar with kaolin clay. The Kaolin clay sample was a special pure product, sourced from a foreign country. The maximum quantity of resins that can be incorporated into the mortar formulation without the packages losing their strength is 13.915% which results in a better mechanical strength at 6.7686 MPA compression with kaolin.


2020 ◽  
Author(s):  
M. Rosário Oliveira

The purpose of this chapter is to present a methodology for developing Control, Measurement and Monitoring Plans. It aims to apply risk-based thinking associated with the works control plan. The failures and rework of the works must not be accepted as inevitable or even as certainties. They must be considered permanent challenges to their management. The importance of using risk assessment techniques in the planning and control of the production activities of the works is evident. Control, measurement and monitoring process should provide the assessment of risks and failures, should demonstrate technical compliance of the work, and should improve operational efficiency. Thus, it is important to define a methodology for the preparation of the Control, Measurement and Monitoring Plan (PCMM), to be implemented in the execution of the works, in order to ensure the conformity of the works with its technical and regulatory requirements. It must establish which the trials and control inspections, its acceptance criteria, its purposes, frequencies and responsible and it must also identify and assess its risks.


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