The 1984-1988 European Communities R&D Programme on Decommissioning of Nuclear Installations was adopted by the EC Council in January 1984 [4] considering:

"Certain parts of nuclear installations inevitably become radioactive during operation; it is therefore essential to find effective solutions which are capable of ensuring the safety and protection of both mankind and the environment against the potential hazards involved in the decommissioning of these installations".

Also, the Council recognized that the 1979-1983 programme of research on the decommissioning of nuclear power plants, of which the 1984-1988 programme is a follow-up, "has yielded positive results and opened up encouraging prospects".

The 1984-1988 programme had the following contents:

• A Research and development projects concerning the following subjects:
• Project n° 1: Long-term integrity of buildings and systems
• Project n° 2: Decontamination for decommissioning purposes
• Project n° 3: Dismantling techniques
• Project n° 4: Treatment of specific waste materials : steel, concrete and graphite
• Project n° 5: Large containers for radioactive waste produced in the dismantling of nuclear installations
• Project n° 6: Estimation of the quantities of radioactive wastes arising from decommissioning of nuclear installations in the Community
• Project n° 7: Influence of installation design features on decommissioning
• B Identification of guiding principles relating to:
• certain guiding principles in the design and operation of nuclear installations with a view to simplifying their subsequent decommissioning,
• guiding principles in the decommissioning of nuclear installations which could form the initial elements of a Community policy in this field.
• C Testing of new techniques under real conditions, within the framework of large-scale decommissioning operations undertaken in Member States:
• pilot projects,
• alternative tests,
• staff secondment.

The research is carried out by public organisations and private firms in the Community under cost-sharing contracts with the Commission of the European Communities.

The Commission budget planned for this five-year programme amounts to 12.1 million ECU.

The Commission is responsible for managing the programme and is assisted in this task by the Management and Coordination Advisory Committee "Nuclear fission energy - Fuel cycle / processing and storage of waste".

The subject of this report is formed by 72 research contracts, including three new contracts concluded in 1988 as well as 42 contracts of which the execution has been completed in 1986, 1987 and 1988.

Subjects of the programme

Section A: Research and development projects

Project/Area Nr. 1: Long-term integrity of buildings and systems

It has been proposed that the dismantling of nuclear installations be delayed for periods ranging from several decades to about a hundred years.

Thereupon, the radioactivity having largely died away, dismantling would be easier and the radiation exposure of the dismantling personnel would be less. The objective of this project is to determine the measures required for maintaining shutdown plants in a safe condition and to assess the radiological consequences and costs.

The work performed under the previous programme relates mainly to the following aspects:

• mode and pace of degradation of various materials as they exist in nuclear power plants;
• measures for maintaining plants in a safe condition and for keeping the necessary ancillary systems operable;
• monitoring and inspection procedures;
• radiological consequences and costs of maintaining the plants.

The work performed under the first five-year programme should be complemented by further tests and the study of control methods relating to the aging of relevant plant materials and by exploitation of additional experience with shutdown nuclear installations.

Project/Area Nr. 2: Decontamination for decommissioning purposes

The objective of this project is to develop and assess techniques for decontaminating surfaces of components and structures of nuclear installations that are past use.

The main purpose of decontamination would be reduction of the occupational radiation exposure during dismantling of the contaminated item and / or reduction of the volume of radioactive waste.

The following decontamination techniques have been developed and assessed:

• techniques based on the use of chemically aggressive decontaminants in liquid and gel-like form;
• electrochemical techniques;
• hydromechanical techniques (high-pressure water lance, erosion by cavitation);
• decontamination of concrete walls by flame spraying.

Other activities were:

• investigation of the characteristics and distribution of contamination in nuclear power plants that are past use;
• economic assessment of decontamination for unrestricted release;
• collection of information on the particular decontamination problems posed by accidental contamination, as in the case of the TMI-2 nuclear power plant.

Selected aggressive decontamination methods should be further developed with a view to their industrial application. Increased effort should be paid to the conditioning of spent decontaminants, where suitable techniques do not yet exist, and to the reduction of secondary waste arisings.

Physical methods that limit the production of liquid effluents might be considered.

An important new topic of the second programme would be the decontamination of hot cells and equipment contaminated with plutonium and other transuranics for purposes of the decommissioning of fuel-cycle installations.

The specific features of such installations (chemical nature of the liquids used during their operation, dimensions of the components, etc.) would be taken into account.

Project/Area Nr. 3: Dismantling techniques

The objective of this project is the development of the special techniques needed for dismantling the large steel components (e.g. reactor pressure vessel) and reinforced-concrete structures (e.g. reactor shielding) of redundant nuclear installations, account being taken of the particular requirements due to radioactivity.

The following techniques have been tested and developed:

• thermal techniques such as plasma-arc and oxygen cutting and cutting by laser beam;
• mechanical techniques such as sawing;
• explosive techniques for the dismantling of concrete structures.

The dismantling techniques needing further development should be chosen account being taken of the results of the first programme.

Particular emphasis will be laid on the minimisation of secondary waste and contamination, and of occupational radiation exposure.

The necessary equipment for the remote operation of dismantling and other decommissioning techniques will be an important new aspect for investigation under the 1984-1988 programme.

Project/Area Nr. 4: Treatment of specific waste materials: steel, concrete and graphite

In the dismantling of nuclear installations large amounts of radioactive steel, concrete and - in the case of gas-cooled reactors - graphite will arise.

This waste must be suitably conditioned for disposal.

The following research work has been performed:

• experiments on the melting of radioactive steel scrap including investigation of the possibility of decontaminating the melt;
• development and assessment of techniques for coating metal and concrete parts in order to immobilise the radioactivity;
• comparative assessment of various modes of treatment and disposal of radioactive graphite.

Melting of radioactive steel should be further investigated, on the one hand as a method for immobilising contamination and reducing the volume of waste, and on the other hand as first step towards the possible recycling of the steel.

The work on coating techniques should be continued with a view to the integration of this treatment into appropriate overall waste management and disposal schemes.

Treatment techniques for graphite waste should be developed for at least one management mode, to be selected with due regard to the results of the assessment performed under the 1979-1983 programme.

The treatment of plutonium-contaminated steel and concrete from the dismantling of fuel-cycle facilities is a new aspect to be investigated under the 1984-1988 programme.

In all these investigations, due attention will be paid to the necessity of adapting the treatment techniques to the final destination of the waste.

Project/Area Nr. 5: Large containers for radioactive waste produced in the dismantling of nuclear installations - Qualification and adaptation of remote-controlled semi-autonomous manipulator systems

Radioactive waste resulting from the dismantling of major reactor components must be transported in larger units than those at present used for other types of radioactive waste, in order to reduce the amount of cutting required and, consequently, the radiation exposure of personnel and the costs of the decommissioning.

A system study has been performed, which made it possible to define the types of large transport and/or disposal container needed for bulky radioactive waste resulting from the dismantling of nuclear power plants.

In the light of the results of the above-mentioned system study, large transport and/or disposal containers should be developed.

The performances of the waste/matrix/container system under conditions representative of envisaged waste repositories should be studied. The control methods for verifying the suitability of the containers for land storage, sea dumping, transport, etc..., according to the specific technical requirements for these different utilisations, will be considered.

Project/Area Nr. 6: Estimation of the quantities of radioactive wastes arising from the decommissioning of nuclear installations in the Community

The low-level radioactive waste produced in the dismantling of nuclear installations will ultimately constitute a substantial part of the overall volume of radioactive waste generated by nuclear industry.

The objective of this area is to estimate the quantities of various categories of radioactive waste that will arise from the decommissioning of nuclear installations in the Community. This involves the definition of reference strategies for decommissioning and is therefore to be regarded as a long-term task.

The following research work has been performed:

• analysis of concrete samples from various nuclear power plants in order to determine the composition and extension of long-lived radio-nuclides in shielding structures;
• analysis of steel samples in order to determine the composition of long-lived radio-nuclides in reactor components;
• preparation of a methodology for evaluating the radiological consequences of the management of very low level waste produced in the dismantling of nuclear power plants;
• review of the measuring techniques required for the purpose of deciding whether or not material from the dismantling of nuclear power plants is radioactive.

Research should be performed in the following main areas:

• improved estimate of the quantities of radioactive waste arising from the decommissioning of typical nuclear installations, account being taken of the results of the first five-year programme (in particular Projects n°2 and n°6);
• study of strategies for the decommissioning of nuclear installations and for the management of the radioactive waste arising therefrom, account being taken of the waste disposal facilities existing or being developed in various member countries;
• characterisation of the radioactivity associated with components and structures of nuclear installations, with emphasis on long-lived radio-nuclides (analyses complementary to those performed under the first five-year programme); in-situ measurement techniques for the localisation and identification of radio-nuclides, including the case of mixtures of alpha, beta and gamma emitters;
• residual activity levels below which activated and / or contaminated parts could be re-used and corresponding measurement methods.

Project/Area Nr. 7: Plant design features facilitating decommissioning

The objective of this project is to identify and develop "reasonable" improvements in the design of nuclear installations with a view to decommissioning.

Activities on the following subjects are in progress:

• control of the cobalt content of reactor steels and testing of cobalt free materials to substitute cobalt alloys;
• surface coatings to protect concrete against contamination;
• reactor shielding design features that facilitate dismantling;
• documentation system for deferred decommissioning;
• review and catalogue of design features facilitating decommissioning.

Some of the subjects studied under the 1979-1983 programme are expected to need continued development under the 1984-1988 programme.

In addition, design features of certain fuel-cycle installations (e.g. reprocessing plants) should be examined with a view to decommissioning.

Section B: Identification of guiding principles

Project/Area Nr. 8: Identification of guiding principles

Section B of the programme is concerned with the identification of guiding principles relating to:

• the design and operation of nuclear installations with a view to simplifying their subsequent decommissioning;
• the decommissioning operations with a view to making occupational radiation exposures as low as reasonably achievable (Alara principle);
• the technical elements of a Community policy in this field.

Hereafter, you can reach the programmes related to this section.

Section C: Testing of new techniques under real conditions

Project/Area Nr. 9: Testing of New Techniques in Practice

In the course of the progressive development of new techniques, ever greater importance will attach to the testing of these techniques under representative conditions, in particular the presence of radioactivity.

Industrial decommissioning operations undertaken in Member States would offer valuable opportunities for such testing.

Because of the importance of this subject, it has been added to the 1984-88 programme as a separate section.

Eleven research contracts relating to Section C were executed in 1988, of which three were completed. These ones can be seen in the following.

References

1. The Community's research and development programme on decommissioning of nuclear installations, First annual progress report (year 1985), EUR 10740, 1986.
2. The Community's research and development programme on decommissioning of nuclear installations, Second annual progress report (year 1986), EUR 11112, 1987.
3. The Community's research and development programme on decommissioning of nuclear installations, Third annual progress report (year 1987), EUR 11715, 1988.
4. Council Decision of 31 January 1984 adopting a research programme concerning the decommissioning of nuclear installations, OJ N° L 36, 8.2.1984, p. 23.

List of projects per Project/Work Area

Project/Area n° 1: Long-term Integrity of Buildings and Systems
FI1D-0030	United Kingdom	Deterioration assessment of nuclear power station buildings
FI1D-0031	Germany	Long-term stability and leak-tightness of reactor containments
FI1D-0032	Germany	1085
Project/Area n° 2: Decontamination for Decommissioning Purposes
FI1D-0001	Germany	Complete decontamination of a primary steam piping of the Lingen BWR
FI1D-0002	Italy	Aggressive chemical decontamination tests on valves from the Garigliano BWR
FI1D-0003	France	Decontamination using chemical gels, electrolytical swab, abrasives
FI1D-0004	Germany	Development of an easy-to-process electrolyte for electropolishing
FI1D-0005	Germany	Optimisation of filtering systems for various concrete decontamination techniques
FI1D-0029	Germany	Economic comparison of decontamination and direct melting with a view to recycling of scrap
FI1D-0033	United Kingdom	Remote electrochemical decontamination for hot cell applications
FI1D-0034	Germany	Decontamination with pasty pickling agents forming a strippable foil
FI1D-0035	France	Racktorch unit for remote decontamination of concrete
FI1D-0063	France	Feasibility of concrete decontamination using a plasma-augmented burner
FI1D-0065	Spain	Closed electro-polishing system for decontamination of underwater surfaces
FI1D-0066	Spain	Development of vibratory decontamination with abrasives
Project/Area n° 3: Dismantling Techniques
FI1D-0006	United Kingdom	Ventilation and filtration techniques for thermal cutting operations
FI1D-0007	France	Pre-filtering devices for gaseous effluents from dismantling operations
FI1D-0008	Scotland	Dross and ultra-fine particulate formation in underwater plasma-arc cutting
FI1D-0009	France	In-situ arc-saw cutting of heat exchanger tubes and of pipes from the inside
FI1D-0010	Germany	Electrochemical technique for the segmenting of activated steel components
FI1D-0011	Germany	Explosive techniques for the dismantling of biological shield structures
FI1D-0012	United Kingdom	Explosive techniques for dismantling of activated concrete structures
FI1D-0013	France	Prototype system for remote laser cutting of radioactive structures
FI1D-0014	Italy	Investigations of applications of laser cutting in decommissioning
FI1D-0036	Germany	Spreading and filtering of radioactive by-products from underwater segmenting
FI1D-0037	France	Development of a prototype system for remote underwater plasma-arc cut
FI1D-0038	United Kingdom	Adaptation of a robot and tools for dismantling of a gas-cooled reactor
FI1D-0039	Germany	Remote measuring and control systems for underwater cutting of radioactive components
FI1D-0040	United Kingdom	Removal of concrete layers from biological shields by microwaves
FI1D-0041	France	Adaptation of an existing air-tight and modular workshop for remote operation
FI1D-0067	France	Adaptation of abrasive water jet to cutting of radioactive steel and concrete
FI1D-0069	Germany	Development of abrasive water jet for submerged cutting of steel
FI1D-0070	Germany	Analysis of results obtained with different cutting techniques
FI1D-0071	France	Analysis of results obtained with different cutting techniques: Associated filtration systems
FI1D-0072	United Kingdom	Measurements of effluents from plasma-arc and laser cutting
Project/Area n° 4: Treatment of Specific Waste Materials: Steel, Concrete and Graphite
FI1D-0015	United Kingdom	Melting/refining of contaminated steel scrap from decommissioning
FI1D-0016	Germany	Melting of radioactive metal scrap from nuclear installations
FI1D-0017	France	Separation of stainless steel constituents using transport in the vapour phase
FI1D-0018	France	Immobilization of contamination on large waste units by polymer coating
FI1D-0042	United Kingdom	Treatment of active concrete dust by slurry setting method
FI1D-0043	Germany	Investigations into the melting of radioactive metal waste in a controlled area
FI1D-0044	Germany	Behaviour of radio-nuclides that are difficult to measure, in melting of steel
FI1D-0064	France	Conditioning for disposal of radioactive graphite bricks from reactor decommissioning
FI1D-0068	The Netherlands	Separation of contaminated cement stone and non-contaminated concrete aggregates
Project/Area n° 5: Large Containers for Radioactive Waste Produced in the Dismantling of Nuclear Power plants - Qualification and adaptation of remote-controlled semi-autonomous manipulator systems
FI1D-0045	United Kingdom	Design and evaluation of large containers for reactor decommissioning wastes
FI1D-0046	France	Large waste containers cast of fibre-reinforced cement
FI1D-0047	Germany	Large waste containers cast of low-level radioactive metal scrap
Project/Area n° 6: Estimation of the Quantities of Radioactive Wastes Arising from the Decommissioning of Nuclear Installations in the Community
FI1D-0019	United Kingdom	Computer programmes for the measurement of low-level gamma contamination
FI1D-0020	United Kingdom	Methods to establish the curie content of waste from decommissioning
FI1D-0021	Germany	System for contamination measurements on curved surfaces
FI1D-0048	Germany	Optimisation of measurement techniques for very low-level radioactive material
FI1D-0049	United Kingdom	Monitoring gamma radioactivity over large land areas using portable equipment
FI1D-0050	France	Radioactive wastes arising from the dismantling of a commercial Fast Breeder Reactor
FI1D-0051	United Kingdom	Methodology for assessing suitable systems for management of reactor decommissioning wastes
FI1D-0052	France	Radiological evaluation of releasing very low-level radioactive copper and aluminium
FI1D-0074	Germany	Methodology and data base for evaluating decommissioning costs and radiation exposure (1)
FI1D-0075	France	Methodology and data base for evaluating decommissioning costs and radiation exposure (2)
Project/Area n° 7: Influence of Installation Design Features on Decommissioning
FI1D-0022	Italy	Decontamination and remote dismantling tests in the ITREC reprocessing pilot plant
FI1D-0053	France	Testing of cobaltfree valve seatings using a special test loop
FI1D-0054	United Kingdom	Pre-stressed concrete reactor vessel with built-in planes of weakness
FI1D-0055	Italy	In-situ sealing of concrete surface by organic impregnation and polymerisation
FI1D-0056	France	Influence of design features on decommissioning of a large Fast Breeder Reactor
Project/Area n° 8: Identification of guiding principles
FI1D-0073	Italy	Dismantling and decontamination of a feedwater preheater tube bundle of Garigliano BWR
Project/Area n° 9: Testing of New Techniques in Practice
FI1D-0023	France	Inventory of information relevant to the identification of guiding principles
FI1D-0024	Belgium	Conditioning, transport and dismantling of very large plutonium glove-boxes
FI1D-0025	Germany	Large-scale application of segmenting and decontamination techniques
FI1D-0026	United Kingdom	Development of techniques to dispose of the Windscale AGR heat exchangers
FI1D-0027	United Kingdom	Pilot decommissioning of a mixed-oxide fuel fabrication facility
FI1D-0028	Germany	Testing of new techniques in decommissioning of a fuel (U, Th) fabrication plant
FI1D-0057	France	Decontamination and dismantling of the PIVER prototype vitrification facility
FI1D-0058	Belgium	Dismantling, partly in situ, of a glove-box structure of a mixed-oxide fuel plant
FI1D-0059	Germany	Melting of radioactive metal scrap from the KRB-A plant
FI1D-0060	France	Volume and plutonium inventories before and after dismantling of a mixed-oxide fuel plant
FI1D-0061	France	Decontamination, before dismantling, of the primary coolant system of the RAPSODIE FBR
FI1D-0062	Germany	Automated measuring system for waste from dismantling of the KKN plant, to be released

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