Belgian Regulatory Framework for Decontamination and Decommissioning: Lessons Learned and New Initiatives

2013 ◽  
Author(s):  
Joris Creemers ◽  
Gilles Hermans ◽  
Virginie Schrayen ◽  
Frederik Van Wonterghem ◽  
An Wertelaers ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Regulatory Framework ◽  
Lessons Learned ◽  
Nuclear Facilities ◽  
Nuclear Power Reactor ◽  
Fuel Fabrication ◽  
Periodic Safety ◽  
Final Shutdown

Belgium can rely on significant experience in the field of decontamination and decommissioning of nuclear facilities. Several projects are ongoing and include research reactors (BR3, Thetis), uranium and MOX fuel fabrication plants (FBFC International, Belgonucleaire), fuel reprocessing facilities (Eurochemic) and radwaste processing facilities (Belgoprocess). Additional projects are expected in the coming years with the planned final shutdown of the oldest nuclear power reactor units. Two national authorities are involved in the decontamination and decommissioning process of nuclear facilities. The FANC (together with its subsidiary Bel V) is concerned for all matters related to nuclear safety and radiation protection, while NIRAS/ONDRAF is concerned for all matters related to radioactive waste and fuel management and financial provisions. These attributions ensure that all safety and material concerns are addressed and that both the licensees and the national authorities bear their own responsibilities. They rely on an existing regulatory framework covering both the procedural and the technical aspects of the decontamination and decommissioning activities. However, opportunities for regulatory improvement were raised after some recent events in Belgium, among which the bankruptcy of a nuclear company producing radioisotopes, involving numerous additional interested parties in a complex judiciary context. Amendments in the current regulations are considered to increase the prerogatives of the authorities regarding the management of radioactive waste by a licensee, the transfer of an operating license from an operator to another, and the general decommissioning strategy of a facility. Furthermore, a dedicated “waste and decommissioning” working group within WENRA defined new reference levels applying to the decontamination and decommissioning of nuclear facilities. Belgium committed to include these requirements explicitly in its national legislation, even though most of them were already included in the existing decommissioning authorizations. Amendments will cover the safety provisions inherent to the decontamination and decommissioning phase, such as the decommissioning strategy, the qualification of techniques, the experience feedback valorization, the periodic safety reviews, the radioactive waste management, or the final characterization of the sites. Additionally, requirements regarding the authorization process will be detailed, such as the content of the licensee’s application file or the structure of the safety report covering the decontamination and decommissioning phase. These changes will contribute to a more secure regulatory framework for all interested parties.

Characterization of Beta Emitters for Decommissioning

2013 ◽  
Author(s):  
Pascal Fichet ◽  
Anumaija Leskinen ◽  
Sylvie Guegan ◽  
Florence Goutelard
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Building Materials ◽  
Liquid Scintillation ◽  
Working Condition ◽  
Nuclear Facilities ◽  
Beta Emitters ◽  
Classical Technique ◽  
Equipment Laboratory

Radioactive waste management is nowadays, after nearly 50 years of concern, a technical and economical challenge faced by existing nuclear power countries. In decommissioning of nuclear facilities after removal of the nuclear equipment (laboratory materials, glove boxes, etc.), the radioactive inventory of the various building materials is needed to state the working condition for dismantling. Thus, characterization is essential for decommissioning and moreover for radioactive waste classification and management. A radionuclide imaging technique, the Digital Autoradiography (DA), also known as storage phosphor technology, has been studied for decommissioning projects because of its advantages such low price, easy utilization and sensitivity. DA has been proven to be an efficient technic in localization of beta emitter (especially C-14 and H-3) contamination remaining in nuclear facilities under dismantling. Samples have been collected where C-14 or H-3 have been observed by DA and analyzed by the classical technique : pyrolysis followed by liquid scintillation counting. Real applications to classify potential waste coming from a laboratory under dismantling are described in this paper.

Low-Level Waste Disposition in D&D: A Systems Engineered Approach

2003 ◽  
Author(s):  
Robert E. Prince ◽  
Dennis P. Ferrigno ◽  
Mark Kirshe
Keyword(s):  
Waste Management ◽  
Complex Systems ◽  
Nuclear Power ◽  
Research Reactor ◽  
Power Reactor ◽  
Lessons Learned ◽  
Nuclear Facilities ◽  
Nuclear Power Reactor ◽  
Waste Production ◽  
Key Factor

When approaching the decontamination and decommissioning (D&D) of a nuclear facility, the key elements of the project are the characterization, dismantlement execution, and the waste management (assay, packaging, transportation, and disposal) tasks. Waste management generally accounts for 40 to 45% of the total cost of the decommissioning project. This paper addresses an effective approach, based on demonstrated experience, to manage the dispostion alternatives for the decommissioning of waste materials. A systems engineered approach will minimize waste production and maximize efficiencies in the decommissioning schedule and offsite waste disposal. A key factor in this approach is to understand the disposal options and the staging criteria permitted within the specific applicable regulatory environment governing the decommissioning. For research reactor, nuclear power reactor, and other nuclear facilities involving complex systems, structures, and components, the key criteria and methodology of this systematic approach are applicable. Duratek has decommissioned numerous power reactor, research reactor, and industrial production facilities involving numerous complex systems and components. This paper focuses on the systems engineered approach, including applicable standards, waste streams, disposition alternatives, waste management methodologies, and lessons learned, for such decommissioning projects.

The Regulatory Framework for Safe Decommissioning of Nuclear Power Plants in Korea

2013 ◽  
Author(s):  
Sangmyeon Ahn ◽  
Jungjoon Lee ◽  
Chanwoo Jeong ◽  
Kyungwoo Choi
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Regulatory Framework ◽  
International Standards ◽  
Current Status ◽  
Nuclear Facilities ◽  
Safety Requirement ◽  
Regulatory Review ◽  
Safety Standards

We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don’t have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA’s safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA’s Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA’s safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards.

scholarly journals Experience in the development and operation of facilities for primary characterization of waste from nuclear facilities

2021 ◽  
Vol 14 (1) ◽  
pp. 39-50
Author(s):  
L. Jbanek ◽  
Keyword(s):  
Decision Making ◽  
Radioactive Waste ◽  
Regulatory Control ◽  
Nuclear Facilities ◽  
Radiation Characteristics ◽  
Waste Characterization ◽  
Measurement Results ◽  
Radioactive Waste Characterization ◽  
The One

The article focuses on methodological and hardware support of radioactive waste characterization, including the one associated with radiation characteristics of materials measured to support the decision-making on its release from regulatory control. The study provides an assessment of uncertainties and their influence on the measurement results. It presents the experience of the Czech company JSC VF in the development of automated installations allowing to address this problem with some examples of such installations operating in various countries being provided.

Experience of Clean-Up Activities and Feedback to Future D&D Projects: Japan Power Demonstration Reactor Decommissioning Project

2001 ◽  
Author(s):  
Satoshi Yanagihara ◽  
Mitsuo Tachibana ◽  
Taro Shimada ◽  
Takenori Sukegawa ◽  
Kunio Shiraishi
Keyword(s):  
Radioactive Waste ◽  
Waste Treatment ◽  
Nuclear Facilities ◽  
Radioactive Materials ◽  
Treatment Policy ◽  
Regulatory Systems ◽  
Building Surfaces ◽  
Radiological Characterization ◽  
Radioactive Waste Treatment

Abstract In the Japan Power Demonstration Reactor (JPDR) decommissioning project, the procedure for clean-up activities was specially studied for harmonization with radioactive waste treatment policy in Japan; it consisted of several components such as survey of the facility operational history, radiological characterization of building surfaces, decontamination and final survey of radioactivities. After confirming that there was no significant radioactivity in the facilities in the final step of the procedure, buildings were demolished in consideration of treatment of wastes as non-radioactive materials. The JPDR decommissioning project was completed by March 1996 with no serious problems, which showed that the procedure was rational, and that the experiences are useful for planning of future decommissioning activities. The dismantling and clean-up activities were reviewed, and the experiences are excepted to contribute to establishing standard and regulatory systems on decommissioning nuclear facilities.

Recent Developments in D&D of Nuclear Facilities in Spain

2001 ◽  
Author(s):  
Juan L. Santiago ◽  
Sergio Vidaechea
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radioactive Waste ◽  
Nuclear Power ◽  
International Level ◽  
Final Phase ◽  
Nuclear Facilities ◽  
Recent Developments ◽  
Leading Position ◽  
Key Issues

Abstract Spain occupies a leading position at international level in the field of installation decommissioning. Decommissioning projects have already been performed in relation to uranium mills, the rehabilitation of disused uranium mines is currently in the final phase and the dismantling of the Vandellós-I Nuclear Power Plant is now under way. On the basis of this experience, this paper describes the key issues in decommissioning technology and presents the approaches adopted by ENRESA to tackle the decommissioning strategy in Spain. In particular practical dismantling and decontamination methods are described, and material and radioactive waste management are discussed.

Spanish Approach to Large Decommissioning Projects

2011 ◽  
Author(s):  
Juan Luis Santiago ◽  
Alejandro Rodri´guez
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Research ◽  
Lessons Learned ◽  
Research Centre ◽  
Nuclear Facilities ◽  
Material Management ◽  
Site Remediation ◽  
Key Aspects

The Spanish experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandello´s I Nuclear Power Plant, the decommissioning of the CIEMAT Nuclear Research Centre and the decommissioning of the Jose´ Cabrera Nuclear Power Plant. This paper reviews the key aspects of these projects and describes the lessons learned related to preparatory activities, auxiliary facilities, decommissioning technologies, material management and site remediation and release.

scholarly journals Concept of a Fast Breeder Reactor To Transmute MA and LLFP

2021 ◽  
Author(s):  
Toshio Wakabayashi
Keyword(s):  
Radioactive Waste ◽  
Power Systems ◽  
Fast Reactor ◽  
Nuclear Power ◽  
Fission Products ◽  
Fast Breeder Reactor ◽  
Nuclear Power Reactor ◽  
The Core ◽  
Effective Use

Abstract The long-term issues of nuclear power systems are the effective use of uranium resources and the reduction of radioactive waste. Important radioactive wastes are minor actinides (MA: 237 Np, 241 Am, 243 Am, etc.) and long-lived fission products (LLFP: 129 I, 99 Tc, 79 Se, etc.). The purpose of this study was to show a system that can simultaneously achieve the breeding of fissile materials and the transmutation of MA and LLFP in one fast reactor. Transmutation was carried out by loading innovative Duplex type MA fuel in the core region and LLFP containing moderator in the first layer of the radial blanket. Breeding was achieved in the core and axial blanket. As a result, it was clarified that in this fast breeder reactor, a breeding ratio of about 1.1 was obtained, and MA and LLFP achieved a support ratio of 1 or more. The transmutation rate was 10.3%/y for 237 Np, 14.1%/y for 241 Am, 9.9%/y for 243 Am, 1.6%/y for 129 I, 0.75%/y for 99 Tc, and 4%/y for 79 Se. By simultaneously breeding fissile materials and transmuting MA and LLFP in one fast reactor, it will be possible to solve the long-term issues of the nuclear power reactor system, such as securing nuclear fuel resources and reducing radioactive waste.

Technologies Used for D&D of the A-1 NPP in Slovakia and Their Comparison With Advanced Worldwide Approaches

2001 ◽  
Author(s):  
Kamil Kravárik ◽  
Vladimír Míchal ◽  
Peter Menyhardt
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Slovak Republic ◽  
Liquid Radioactive Waste ◽  
Nuclear Regulatory Commission ◽  
Technical Level ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
Regulatory Commission

Abstract This paper deals with technologies used for decommissioning and decontamination of the A-1 Nuclear Power Plant in Slovakia and their comparison with advanced worldwide approaches. Present status and main results in the field of D&D of this first Czechoslovak NPP A-1 at Jaslovské Bohunice are described. NPP A-1 has one unit with reactor cooled by CO2 and moderated by heavy water. Plant was in operation from 1972 to 1977 and its final shutdown and closure were done due to relatively serious accident. The A-1 NPP Decommissioning Project – I. phase is performed at the present time and represents the most important project of NPP decommissioning in Central Europe. The main goal of the project is to achieve radiologically safe status of the NPP. It includes following activities: • conditioning, storage and disposal of liquid radioactive waste, solid and metallic radioactive waste, sludge and sorbents, • development, manufacture and verification of advanced methodologies and technologies for D&D of nuclear facilities, • decontamination of specified equipment and structures to reduce free activity, • technical support and preparation of following phases within the A-1 NPP overall decommissioning process. The project should give the complex solution of problems related to decommissioning and decontamination of NPPs in Slovakia. Verified methodology and technology should be used as a generic approach for decommissioning of the V-1, V-2 (Jaslovské Bohunice) and Mochovce Nuclear Power Plants as well as the other European NPPs with WWER reactors. Significant part of paper deals with following issues within D&D of the A-1 NPP: • computer aided technologies, • decontamination, • dismantling, demolishing and remote handling manipulators, • dosimetry measurements within D&D, • radioactive waste management. This paper also includes basic comparison with advanced worldwide approaches to decommissioning and decontamination mainly in USA, Japan and West Europe and the recommendations are done when it is possible. The comparison shows that trends in the field of D&D in the Slovak Republic are compatible and comparable with the most significant world trends. It is noted that some sorts of D&D technologies like for example telerobotic systems developed in the world are at the relatively higher technical level. Decommissioning technologies in Slovakia should be permanently improved on the base of experiences from home and abroad industry and from the real operation. It is supposed that after short time could be achieved technical level comparable with the best D&D robots and manipulators. A basic strategy of NPP decommissioning in the Slovak Republic is regulated by standards, which are in accordance with recommendations of international bodies like the International Atomic Energy Agency, European Commission, U.S. Nuclear Regulatory Commission, OECD Nuclear Energy Agency etc. In the field of NPP D&D the Slovak Republic co-operates with many international organizations and also with main active countries in D&D like Germany, France, Belgium, Great Britain, USA, Japan, Russian Federation, Hungary, Poland and Czech Republic. Intensive international co-operation at all levels has already been established at the present time.

Characterization of aerosols from dismantling work ofexperimental nuclear power reactor decommissioning

1991 ◽  
Vol 22 ◽  
pp. S747-S750 ◽  
Author(s):  
J. Onodera ◽  
H. Yabuta ◽  
T. Nishizoro ◽  
C. Nakamura ◽  
Y. Ikezawa
Keyword(s):  
Nuclear Power ◽  
Power Reactor ◽  
Nuclear Power Reactor
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