– investigation of thermal processes in energy equipment components:
– forced and mixed convection, turbulent and transition flow regimes, influence of channel geometry, variable physical properties, roughness, centrifugal forces and transients effect;
– numerical modelling of heat transfer in various channels and geological structures;
– reduction of emission resulting along with smoke from biofuel combustion using electrostatic filters; research of heat and mass transport in the equipment of biofuel-fired objects;
– safety of spent nuclear fuel (SNF) management: modelling of fuel characteristics, safety and environmental impact assessment of storage and disposal facilities, normative and legislative base;
– safety of radioactive waste management: strategy, safety and environmental impact assessments of treatment storage and disposal facilities, normative and legislative base;
– evaluation of different factors related to decommissioning of nuclear power plants: planning and cost of decommissioning and dismantling, radiological characterisation of buildings, systems and facilities, safety and environmental impact assessment, normative and legislative base;
– fire hazard analysis of nuclear power plants and other facilities;
– research related to construction of new nuclear power plant in Lithuania.
Experts of Nuclear Engineering Laboratory together with other laboratories of the Institute are coordinating and implementing two long-term scientific research and experimental development programs, which were approved by the Ministry of Education and Science of the Republic of Lithuania at the beginning of 2012:
• Investigation of single-phase and two-phase flow dynamics, heat and mass transfer processes (2012– 2016). The objective of the program – to develop research methods and perform investigations of single-phase and two-phase flow structure, heat and mass transfer, in dealing with the efficiency of new heat energy production from biofuel schemes, energy and mass flow measurement and heat and mass transfer intensification tasks under flow non-stationary, transient,
impact of physical features and thermo gravitational forces and vapour condensation processes.
• Investigation of nuclear power plants’ decommissioning and radioactive waste and spent fuel management processes and radiation impact analysis (2012–2016). The objective of the program – to analyze and estimate radiation impact on humans and environment during management, storage and disposal of SNF and radioactive waste with application of numerical and experimental research methods and taking into account the peculiarities of Ignalina NPP decommissioning.
Research of thermal processes in energy equipment components
Laboratory carries out investigations of heat transfer and hydrodynamics in energy equipment for different purposes (in the elements of nuclear reactor, various heat exchangers, etc.). Since in both laminar and turbulent flow cases, the effect of thermogravitational forces (mixed convection) on heat transfer is manifested in many energy facilities, which under certain conditions can be the reason for an accident in different facilities. For this reason, the Laboratory performs experimental mixed convection investigations in pipes and has initiated the research in flat channels as well. Additionally, such research was initiated in geological structures while analysing the possibilities of Ignalina NPP spent nuclear fuel disposal. In parallel, research is also performed using the ANSYS FLUENT code (ANSYS, USA) which is widely used worldwide for modelling the fluids flow and heat transfer in complex two and three-dimensional systems. The Laboratory uses various models of the laminar, transition and turbulent transfer.
In 2012 the numerical investigations (using ANSYS FLUENT code) on heat transfer and hydrodynamics in flat channel for opposing mixed convection flows in the transition region were continued. The obtained heat transfer and flow hydrodynamics results expand the understanding on the transition from the laminar to turbulent flow under the impact of thermogravitational forces.
Advanced countries pay a lot of attention to the reduction of negative environmental impact caused by various energy objects. The reduction of pollution is an especially relevant issue in solid fuel combustion and one of the means to achieve it is the use of electrostatic filter (precipitator). It is an effective means for cleaning the emitted solid particles (especially small ones which are not captured by other filters (e.g.: cyclonic filters)). Electrostatic filters intended for deposition of solid particles and used in industrial and energy equipment are prevailing worldwide for reducing the environmental pollution down to minimum. The filters are usually used in medium or high capacity power plants fired by coal or similar type of fuel. These filters are also relevant for specific industrial companies (concrete production, waste incineration power plants, etc.) which emit hazardous materials together with smoke during the production process. The novelty lies in the combustion of different types of biofuel since depending on the burnt material, the operation (efficiency) of filters changes due to the influence of different sizes and composition of particles emitted with smoke. An exhaustive analysis of these factors enables solving relevant issues related to upgrading technologies of the Lithuanian energy sector.
In 2012 researchers of the laboratory in frame of the project Investigation of local fuel thermal decomposition processes in developing efficient and ecological technologies (2012–2014), financed by national science program Future Energy of Research Council of Lithuania, together with other laboratories of the institute conduct the following research. In 2012 scientific and practical demands fields’ analysis of biofuel combustion products cleaning research was carried out with the aim to determine research fields and expansion possibilities. The facility was designed at the laboratory to perform such investigations.
In 2012 participating in Santaka valley project Foundation of National Open Access Scientific Center for Future Energy Technologies the laboratory was equipped with LDA and PIV equipment devoted to investigate flow structure in gas and fluids in wide velocity variation limits. This equipment is able to measure velocities and their pulsations, frequency of vortex rotation, to visualize them, etc. Also the laboratory purchased liquid crystal thermography facility, which enables to measure temperature of different objects as well as the variation of temperature of separate investigated object image parts by remote non-invasive method.
Safety of spent nuclear fuel management
After the decision to use dry storage of spent nuclear fuel (SNF) at Ignalina NPP in CASTOR and CONSTOR type casks, the Laboratory started performing studies related to the safety assessment of SNF management, storage and disposal in 1997. The Laboratory carried out criticality assessments for the casks with SNF under normal operational and accident conditions, variation of radionuclides activity during the storage period, radiation doses on the cask surface and at the specific distance from it as well as temperatures of the cask.
Implementing the research on SNF disposal in Lithuania, the Laboratory experts with the assistance of Swedish experts proposed the concepts of deep geological repository in clay and in crystalline rocks for SNF and long-lived intermediate level waste in Lithuania. The concepts on disposal are constantly defined more precisely and optimised taking into account international experience and physical, chemical, thermal and mechanical properties of a specific repository site. While analysing the possibilities of SNF disposal in Lithuania, the costs assessment of geological repository installation was carried out and generic repository safety assessment was initiated.
In 2012 a scientific project Probabilistic Uncertainty Assessment of Radiation Impact during the Analysis of NPP Dismantling and Radioactive Waste Managing (2010–2012) financed by the state budget grant was finalized. The research on the radionuclide migration from deep SNF repository in case of container defect scenario was performed. The scenario assumes that a disposal container with a small defect (untightness) in its wall may pass the inspection by non-destructive control methods and be disposed of in the repository. Thus, radionuclide transport from disposal container through the wall defect is modelled. Having spread from the container, the radionuclides migrate through the bentonite layer (engineering barriers) and diffuse to the groundwater, which flows in the fracture intersecting the tunnel in crystalline rocks.
During the investigations, the model of radionuclide migration from RBMK-1500 SNF deep repository was developed in order to evaluate the impact of uncertainty, related to the increase of container wall defect, migration on the separate radionuclide from the container. In 2012, the inpact of defect enlargement time and other parameter uncertainty on the assessment results of long-lived radionuclide 129I and 226Ra migration (the average and the maximal flux) was analysed. Sensitivity analysis of time dependant radionuclide flux and maximum radionuclide flux was performed, the parameters having the largest impact at predefined time were identified.
The probabilistic assessment of radionuclide migration demonstrated that in order to optimize the analysis of radionuclide 129I transport through engineering barriers, it is worthwhile to concentrate the further research on the parameters defining bentonite diffusion, instant release fraction and SNF matrix dissolution rate. In the case of 226Ra the revision of the SNF matrix dissolution rate, bentonite sorption coefficient and the equivalent flow rate of groundwater is recommended.
It was also determined that the defect enlargement time uncertainty has no significant impact on radionuclide 129I and 226Ra maximal flux outside the repository engineering barriers, however it is significant for the average flux of 129I. It was also determined that the defect enlargement time uncertainty has no significant impact on radionuclide 129I and 226Ra maximum transport behind repository engineering barriers, however it is significant from the perspective of 129I average transport.
Furthermore, complex investigations of the influence of heat transfer and mechanical processes in natural and engineering barriers under unsaturated conditions were continued. Numerical research was carried out using software COMPASS (GRC, United Kingdom), whereas radionuclide migration was evaluated applying softwares AMBER (Quintessa, United Kingdom), PETRASIM (USA), COMPULINK, CHAN3D, PREBAT-BATEMAN (SKB, Sweden).
In 2012 the research of gas migration from deep SNF repository was continued. Gas in the repository will be generated due to corrosion of steel (engineering components and disposal containers), whereas their amount will depend on the type of radioactive waste and the selected disposal concept. This research is performed together with 23 partners from 10 EU countries under the project Fate of Repository Gases (FORGE)(2009–2013) financed by the 7th Framework Programme (FP7) of the EU. In 2011 a gas migration model in single disposal tunnel was developed and numerical modelling was carried out using PETRASIM (USA) software package. The values of parameters important from the perspective of repository safety – maximum gas pressure and gaseous fluxes (from disposal tunnel to the transportation tunnel) – were determined. In 2012 sensitivity analysis of these results was performed – it was estimated which factors influence their increase or reduction. The obtained results correlate with the modelling results of the project partners.
In 2012, as a partner of consortium GNS – NUKEM Technologies GmbH (Germany), the Laboratory continued an extensive project Design and Installation of the Interim Storage Facility for RBMK Spent Nuclear Fuel Assemblies from Ignalina NPP Units 1 and 2(2005–2011). This project comprises the analysis of all activities related with the design, construction, installation, commissioning, operation and decommissioning of the new SNF storage facility and the performance of all necessary works related to the SNF removal, packaging, sealing and transfer as well as operation of the appropriate equipment for implementation of chosen design concept. It is planned to store approximately 200 new type CONSTOR casks with intact and damaged SNF in the new storage facility.
The Laboratory prepares Environmental Impact Assessment and Safety Analysis Reports of this SNF storage facility (operational time no less than 50 years) and offers support in licensing the storage facility. In 2007, Environmental Impact Assessment Report was approved by the Ministry of Environment; in 2009, Preliminary Safety Analysis Report (PSAR) was prepared and agreed upon and the licence for construction of the new SNF storage facility was issued by VATESI. In 2010-2011, PSAR Addendum, which presents the evaluation of safety aspects of damaged RBMK-1500 nuclear fuel assemblies’ management and storage, was being prepared.
Safety of radioactive waste management
Since 1994 the Laboratory has been actively involved in the analysis of the radioactive waste management problems at Ignalina NPP. Laboratory experts together with the experts from SKB International (Sweden) carried out a number of projects, which included safety assessment of existing waste storage facilities and the possibilities to transform them into repositories. Together with French companies Thales Engineering and Consulting, ANDRA and the Institute of Physics, PHARE project Safety Assessment and Upgrading of Maišiagala Repository in Lithuania was implemented. The Laboratory specialists participated in preparing Safety Analysis Report, developed the database containing information on the radioactive waste, which is stored in the Maišiagala storage facility, and performed a comprehensive nuclide composition analysis. The Laboratory together with Framatome ANP GmbH (Germany) participated in executing the environmental impact and safety assessments for Ignalina NPP cement solidification facility and a temporary solidified radioactive waste storage facility. Additionally, the Laboratory constantly participates in the research programmes coordinated by IAEA.
In recent years, a great deal of attention was devoted for the siting of a new near-surface repository of radioactive waste in Lithuania, and for scientific research related to the radionuclide migration from radioactive waste repositories and its impact on safety. With the assistance of Swedish experts, the Laboratory specialists prepared the set of criteria for choosing a near-surface repository site, improved the reference design of a near-surface repository and prepared the implementation programme. The impact of heterogeneous waste activity distribution on radionuclide migration from model near-surface repository was investigated.
Numerical research was carried out using software DUST (BNL, USA), GENII (PNNL, USA), GWSCREEN (INEEL, USA), and AMBER (Quintessa, UK).
During 2006–2009, the Laboratory specialists implemented the project Reconstruction of Ignalina NPP Bitumen Radioactive Waste Storage Facility (Building 158) into Repository. A long-term safety assessment of the planned repository was prepared; it was based on the possible engineering solutions of storage facility reconstruction into repository, components of disposal system. To be more precise, radioactive waste, storage facility and surface engineering barriers planned to be installed over storage facilities and site characteristics were taken into consideration.
In 2012, the Laboratory together with NUKEM Technologies GmbH (Germany) continued the project New Ignalina NPP Solid Waste Management and Storage Facility (2006–2013). This facility is intended for solid radioactive waste retrieval, sorting, transportation, treatment (using envisaged technologies), packaging, characterisation and storage. The facility comprises the solid waste retrieval facility located at the existing INPP solid waste storage buildings, the new solid waste treatment facility, the new short-lived radioactive waste storage facility and the new long-lived radioactive waste long-term storage facility.
The Laboratory prepares environmental impact assessment and safety analysis reports for this complex. Environmental Impact Assessment Report was agreed upon and approved by the Ministry of Environment in 2008 and two PSARs, New Solid Waste Treatment and Storage Facilities at Ignalina NPP and New Solid Waste Retrieval Facility at Ignalina NPP were prepared. The former was approved in 2009 and VATESI issued the licence for the construction of the facility. Additionally, in 2009 two more PSARs, New Solid Waste Retrieval Facility. Retrieval Unit 1 and Retrieval Unit 2-3 at Ignalina NPP was newly prepared, while in 2010 both PSARs were submitted to authorities for review. The former was updated following the recommendations of the authorities and approved by VATESI in the end of 2010, while in the middle of 2011, the licence to build the facility was issued. The second PSAR was modified considering the recommendations of the authorities in 2011–2012.
In 2012, the Laboratory, as a partner of Lithuanian consortium (JSC Specialus montažas-NTP, LEI, Pramprojektas, JSC Vilstata) continued implementing the project Installation of Very Low Level Radioactive Waste Repository (Landfill) (2008–2010). Landfill repository is intended for disposal of very low-level radioactive waste generated during Ignalina NPP operation and decommissioning. Landfill facility will be comprised of three repository modules and buffer storage where waste will be stored till their disposal. The Laboratory prepared Environmental Impact Assessment Report for the planned economic activity (approved by the Ministry of Environment in 2009) and two PSARs, The Buffer Storage of the Landfill Repository (approved by VATESI in 2009) and The Disposal Modules of the Landfill Repository (agreed with VATESI in 2010). General Data Set on the Buffer Storage of the Landfill Repository was completed (approved by the European Commission in 2010), whereas in 2011 General Data Set on the Disposal Modules of the Landfill Repository was submitted to the European Commission for review.
In 2012 Waste Package Specifications (WPS) for three types of radioactive waste packages, namely compressible waste, non compactable waste and spent ion exchange resins, intended for the final disposal in the very low activity radioactive waste repository, were prepared,. The WPS were agreed with Radioactive Waste Management Agency (RATA) and State Nuclear Safety Inspectorate (VATESI). The experts of the laboratory elaborated final safety analysis report (FSAR) for Landfill repository buffer storage. FSAR submitted to VATESI for approval.
Last year, the Laboratory together with partners from French companies AREVA TA and ANDRA and Lithuanian partners JSC Specialus montažas-NTP and Pramprojektas continued the project Low and Intermediate-Level Short-Lived Radioactive Waste Near-Surface Repository (Design) (2009–2013). The repository is intended for disposal of low and intermediate-level short-lived radioactive waste generated during Ignalina NPP operation and decommissioning.
In 2010–2011, the specialists of the Laboratory made a considerable contribution to the preparation of Design Concept Report, Waste Inventory Report and Site Revalidation Report which were submitted to the Contractor and approved. In 2012 Basic Engineering Design report for Near surface repository for low and intermediate-level short-lived radioactive waste near-surface repository was prepared and submitted. For this report the experts of the laboratory prepared four chapters: description of waste, long-term safety assessment, waste acceptance criteria and waste package specifications as well as general overview of environment monitoring and repository surveillance. In 2012 preparatory work of technical project was initiated during which the experts will estimate long-term repository safety and will prepare chapters of preliminary safety analysis report. Preparation of environment monitoring program and coordination with the responsible state institutions is foreseen for 2013.
The Laboratory continued the previous research of radionuclides migration from near surface repositories. In 2011 in the scope of the scientific research Probabilistic Uncertainty Assessment of Radiation Impact during the Analysis of NPP Dismantling and Radioactive Waste Managing (2010–2012) they analysed the migration of separate radionuclides from near-surface repositories in order to evaluate the factors which have the largest impact on the uncertainty of the obtained results. Parameter sensitivity analysis was performed and most significant parameters influencing the radiation impact uncertainty were determined.
In 2012 during the implementation of the above-mentioned budgetary work and the project Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste (CARBOWASTE) (2008–2013) of the 7th Framework Programme of the EU, numerical research related to the radiological characterization of the constructional materials of RBMK-1500 reactor, namely irradiated graphite, was continued. In 2012, the modelling of axial neutron flux distribution was continued: the axial activity distributions of the main radionuclides in activated graphite were estimated, and the possible spread of their activity values was analysed regarding the amount of initial impurities. Having obtained the initial measurement results of the activity of several radionuclides in the graphite sleeve of Ignalina NPP Unit 1 reactor, the calibration of the developed models was carried out. Similarly as before, the numerical research was performed using MCNP-5 (LANL, USA) and ORIGEN-S (from SCALE-5 software system) (ORNL, USA) software.
The feasibility study of RBMK-1500 graphite final disposal in a repository was analysed in the scope of CARBOWASTE project regarding the alternatives of treatment/non-treatment of the graphite. To assess the specificity of long-term repository operation after placing irradiated graphite, numerical models were developed. While performing numerical modelling the release of radionuclides from graphite and their transport through engineering barriers of the repository was evaluated. The developed models of the repository environment were implemented using AMBER software (Quintessa, the United Kingdom). The analysis of radionuclide transport was carried out taking into account the results obtained within the mentioned project, whereas aiming to estimate the relation between waste treatment and final disposal, the relation between radionuclide release rate and maximum radionuclide flux outside the repository engineering barriers was analysed.
During the analysis possible different functioning of engineering barriers was considered and numerical modules of radionuclide migration were developed, when graphite waste is emplaced in the disposal contained without grouting and grounted in cementitious grout, estimating in this way the impact of immobilization in cement material. For further assessment of migration in natural environment numerical models were realized in the environment of software TOUGH (LBNL, USA), and the impact of natural barriers on radionuclide migration was estimated.
Evaluation of different factors related to decommissioning of nuclear power plants
In 2007–2010, Lithuanian Energy Institute, as a partner of consortium VT Nuclear Services Ltd (UK) – LEI – NUKEM (Germany), implemented the project Ignalina NPP Building 117/1 Equipment Decontamination and Dismantling. In 2009 the specialists of the Laboratory prepared Environmental Impact Assessment Report approved by the authorities, while in 2010 they completed General Data Set, Basic Design and Safety Justification Report; the two latter were approved by the relevant authorities. The researchers of the Laboratory also participated in preparing the Detailed Design, which was reviewed and submitted to the contractor. The characteristics of the equipment of building 117/1, waste amounts and their characteristics were analysed and economic assessment of the planned decontamination and dismantling activities was carried out by laboratory specialists. Following the prepared documentation, the INPP started the work of dismantling and decontamination of equipment installed in Building 117/1 on 1 December 2010 and completed them in October 2011.
In 2012, Lithuanian Energy Institute, as partner of consortium Babcock (UK) – LEI – NUKEM Technologies GmbH (Germany), completed the project Ignalina NPP Building V1 Equipment Decontamination and Dismantling (2009–2012). In 2010 Specialists of the Laboratory completed General Data Set; in 2011 they prepared Environmental Impact Assessment Report and received its approval from the Ministry of Environment, whereas in 2012, Basic Design and Safety Justification Report were agreed with the authorities, whereas the Detailed Design was completed in 2012. The employees of Ignalina NPP initiated dismantling and decontamination activities of Ignalina NPP building V1.
In 2009, the specialists of the Laboratory developed DECRAD software intended for the analysis of decontamination and dismantling of nuclear power plants, planning the demand for expenses, costs and personnel, calculation of the personnel radiation doses, planning of radioactive waste disposal and the assessment of other parameters related to the decommissioning. The software may be applied for planning and analysing decommissioning of different power plants, their separate buildings or units. In 2012, the specialists upgraded the software code DECRAD. It was successfully applied in the scope of the project Ignalina NPP Building V1 Equipment Decontamination and Dismantling.
In 2012 performing project CARBOWASTE multi-criteria decision analysis methodology was acquired. The analytic hierarchy process was identified as the most effective method for choosing nuclear equipment dismantling strategies. Nuclear equipment dismantling strategies were developed, whereas a list of qualitative and quantitative criteria, comprised of higher level criteria (waste flows, expenses, duration, safety, technological, environmental and social) and lower level criteria, was developed. Primary data was processed and quantitative criteria values for different dismantling strategies were estimated applying software package DECRAD. The analysis of dismantling strategies and strategies’ ranking results were obtained by applying AHP method. The investigations were expanded in previously discussed state budget financed scientific project, where probabilistic assessment of uncertainty of alternative ranking relative weights was carried out as well as sensitivity analysis of alternatives’ relative weights.
One of the most important tasks for the shutdown of NPP is safe dismantling of the equipment. Due to the shutdown Ignalina NPP Unit 1 in 2004 and Unit 2 in 2009, the analysis of the mentioned issues and suitable solutions are especially important. Apart from the already-mentioned specificities, in 2011 a probabilistic uncertainty assessment of radiation impact on the personnel dismantling the pipelines of the Ignalina NPP emergency cooling system was carried as part of the project Probabilistic Uncertainty Assessment of Radiation Impact during the Analysis of NPP Dismantling and Radioactive Waste Managing (2010–2012).
Two alternatives of pipelines dismantling were analysed, the efficiency of respiratory safety measures was estimated as well as their impact on the general effective dose of the sawyer. Computer software VISIPLAN (Belgium) was applied while estimating the direct effective dose of the sawyer from radioactive equipment.
In 2012, Lithuanian Energy Institute, as a partner of international consortium (JSC Specialus montažas - NTP – FTMC – LEI – ATP (Bulgaria) – INRNE (Bulgaria) – VNIIAES (Russia) started a project Evaluation of the Material Backlog and Radiological Inventory of Kozloduy NPP Units 1 to 4. The objective of the project is to carry out a detailed evaluation of the radiological status of the equipment, structures, compartments and the radioactive waste and assess the total radiological inventory and material backlog of the units under decommissioning.
In 2012 the experts of the laboratory developed database to accumulate project results and provided technical assistance to consortium partners.
Since 2002, the Laboratory is performing fire hazard assessments in the nuclear power plants and other important facilities. In consultation with Swedish experts, the Laboratory specialists assessed the fire hazard of Units 1 and 2 of Ignalina NPP. Fire hazard assessment of some renewed INPP rooms and newly designed INPP SNF and radioactive waste storage facilities were carried out as well. An external fire impact on the new INPP facility for solid waste treatment and storage was assessed and the fire hazard analysis of the most dangerous areas in the case of an internal fire was performed. In 2009, the impact of fire during the implementation of Ignalina 117/1 building dismantling and decontamination was evaluated as well as the fire safety of newly designed buffer storages and disposal units of Landfill repository was analysed. In 2010, the impact of fire during the implementation of Ignalina V1 unit dismantling and decontamination was assessed. In 2012 report on B19 facility (Buffer storage of the Landfill repository) fire hazard analysis based on detailed project documentation was updated in project Installation of very low activity radioactive waste repository (Landfill). This report was approved by the authorities in 2012.
Research related to the construction of a new nuclear power plant in Lithuania and other international activity of the Laboratory
In 2007–2009, in consortium with Pöyry Energy Oy (Finland), the Laboratory specialists carried out the research related to the construction of new nuclear power plant in Lithuania. The Environmental Impact Assessment Programme for New Nuclear Power Plant and New Nuclear Power Plant Environmental Impact Assessment Report were prepared. In the EIA Report, possible environmental impacts of the construction and operation of new NPP were assessed in cooperation with other Finish and Lithuanian institutions (Institute of Botany, Institute of Ecology and National Public Health Surveillance Laboratory). According to the EIA Report of 2009, positive conclusions of the competent authorities were made concerning the planed economic activity and, therefore, following this EIA Report, the Ministry of Environment has made a motivated decision on the construction possibilities of new nuclear power plant.
The researchers of the Laboratory are participating in the research projects coordinated by IAEA, namely:
• Treatment Requirements for Irradiated RBMK-1500 Graphite to Meet Disposal Requirements in Lithuania (2010–2014).
• Investigation of RBMK-1500 Spent Nuclear Fuel and Storage Casks Performance during Very Long Term Storage (2012–2016).
Researchers of the laboratory are participating in four EU’s 7th Framework Programme funded projects. Two of them are scientific research projects (they are already mentioned above):
• Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste (CARBOWASTE) (2008–2013).
• Fate of Repository Gases (FORGE) (2009–2013).
The remaining two – coordination and support action projects:
• New MS Linking for an Advanced Cohesion in Euratom Research (NEWLANCER) (2011–2013). The project is performed by the experts of the laboratory in cooperation with 15 partners from 9 European countries. The main objective of the project is to analyse the research potential of EU new member States and promote scientific cooperation with the EU old member States. In 2012 national and regional meetings of experts took place in Hungary and Bulgaria, during which the course of activities, results and future perspectives were discussed. The representative from LEI in these meetings presented the overview of Lithuanian science research institutions participation in EURATOM program as well as the results of strength, weakness, possibilities and hazards’ analysis performed by LEI experts, national strategies and programs in the field of radioactive waste and spent nuclear fuel management.
• Sustainable network of Independent Technical Expertise for Radioactive Waste Disposal (SITEX) (2012–2014). This project is performed together with 15 other organizations from the EU countries, Canada, the Netherlands and Sweden. Its main objective is to identify efficient means to implement for the establishment of a European sustainable network of independent technical expertise in the field of radioactive waste disposal. It is intended for strengthening general and mutual understanding of different aspects regarding repository safety among the regulatory institutions and organizations providing technical safety expertise and waste management. The network also aims at assessing the demand for independent scientific research, recommendations for technical expertise, etc. In 2012 the comparison of the repository safety related requirements, recommendations, technical expertise methodologies were carried out.
In 2012 the Laboratory (26 employees) completed a state subsidy funded research work Probabilistic Uncertainty Assessment of Radiation Impact during the Analysis of NPP Dismantling and Radioactive Waste Managing (2010–2012), and also the project Ignalina NPP Building V1 Equipment Decontamination and Dismantling (2009–2012), in which laboratory experts were participating, was finalised.
Researchers of the laboratory carried out 13 applied research projects and earned almost 2 million LTL. Researchers of the laboratory were improving their qualification by actively participating in different training programmes and coordinating meetings. They presented 7 papers at international conferences (Malta, Belarus, France, Japan and Lithuania) and published 14 scientific articles in the Lithuanian and international journals.
On the open days at Lithuanian Energy Institute senior research associate Dr. R. Poškas presents the activities of the Laboratory to students (10 September 2012, LEI)
The representative of equipment manufacturer training the laboratory scientist how to use the equipment purchased under the framework of Santaka valley project
(02 February 2012, LEI)
Dr. A. Narkūnienė during IAEA training course on Identifying and managing uncertainty for post-closure safety assessments in support of repository development programs (16-23 June, 2012, Portugal)
DPhD student D. Justinavičius with the representatives from other countries in experimental research tunnel at the clayey environment (IAEA training courses,
09-16 September 2012, Tournemire, France)
Variation of gas pressure Pg in disposal tunnel of radioactive waste
“Hot” tests of container conducted at the Buffer storage of the Landfill repository
Dr. R. Kilda and Dr. V. Ragaišis at the meeting with partners at AREVA‘s headquarters
(14 November, France)
G. Poškas and Dr. A. Šimonis at international conference ICRS-12 (02-07 September 2012, Nara, Japan)
Dr. A. Šmaižys at NEWLANCER meeting at the Hungariane Academy of Sciences (02 April, 2012, Budapest, Hungary)
Dr. A. Narkūnienė and G. Poškas at SITEX meeting at IAEA‘s headquarters (24 May, 2012, Vienna, Austria)