RATEN ICN CONTRIBUTION IN INTERNATIONAL PARTNERSHIPS
FOR NUCLEAR DEVELOPMENT
presented by Cristina Alice Mărgeanu RATEN ICN Piteşti, ROMANIA
18– 21 May 2021
18th INPRO Dialogue Forum on Partnerships for Nuclear Development and Deployment
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CONTENT
European Lead Fast Reactor, Generation IV project
FP7 / MAXSIMA Project
IAEA Coordinated Research Projects
IAEA INPRO Collaborative Projects and activities
EURATOM Projects supported by NUGENIA
- SARNET Network of Excellence on severe accidents
- NET Network on Neutron Techniques Standardization for Structural Integrity
Conclusions
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European Lead Fast Reactor, Generation IV project (1) International partnership for LFR and ALFRED Focus on the development of the LFR demonstrator (technical
and economic viability) ALFRED Demonstrator, 125 MWe, connected to grid Evolution :
• 2011, Romania expressed the interest to host ALFRED • 2013, FALCON international consortium set-up • 2014, nuclear platform Mioveni as reference site • 2018, RATEN ICN notified the regulatory body on the
pre-licensing phase • 2020, starting the construction of relevant licensing and RDI infrastructure
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European Lead Fast Reactor, Generation IV project (2) FALCON Consortium (Fostering ALFFED Construction) Objective : Deployment of a LFR demonstrator having SMR-oriented features aimed at being a
competitive option for the future NPPs (replacing the old generation NPPs facing retirement or conventional technologies based on fossil fuels), as well as longer-term potentialities to demonstrate that the LFR technology can meet the goals set out by GIF for Generation-IV reactors
ALFRED Advanced Lead-cooled Fast Reactor European
Demonstrator
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European Lead Fast Reactor, Generation IV project (3) FALCON Partners and Supporting Organizations
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European Lead Fast Reactor, Generation IV project (4) Efforts for synergy RDI, E&T
National R&D Projects
Improvements of national capabilities for nuclear
innovative systems
Lead School
CESINA = Partnership for Cooperation on Nuclear Advanced Systems, RDI E&T - Stimulate cooperation and synergy - Boosting Education &Training
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European Lead Fast Reactor, Generation IV project (5) ALFRED, FALCON Consortium (2013)
The Roadmap
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European Lead Fast Reactor, Generation IV project (5) ALFRED in strategic documents
Local/Regional: Smart Specialization Strategy
Socio-economic development: Jobs, economic growth, keep young talents, strengthen the economic poles of development
Energy security: Stability and sustainability, high efficiency, flexibility, low carbon emissions by advanced technologies Industrial development: keep competencies, business development RDI: Enlarge national RD infrastructure, synchronism with major themes, international cooperation
Technological development: future deployment of GenIV systems
National: RDI Strategy, NECP, Roadmap of major RIs
EU: SET Plan-A10(Nuclear) SNETP-SRIA
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European Lead Fast Reactor, Generation IV project (6) Recent Advancements
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European Lead Fast Reactor, Generation IV project (7) Experimental infrastructure
New large facilities for Licensing process: ATHENA, large pool to test the main components in different thermal hydraulics regimes ChemLab, lab coupled with ATHENA, lead and cover gas chemistry HELENA2, loop type facility to test components and equipment in relevant thermal-
hydraulic conditions, in particular, the ALFRED hottest fuel assembly ELF, large scale pool-type facility, to test the endurance and reliability under both forced
circulation and natural circulation regimes HandsOn, pool type experimental facility,
to demonstrate the fuel handling of fuel assemblies Meltin’Pot, set of facilities to investigate
the fuel-coolant interaction, fuel dispersion and relocation in the coolant resulting from a severe accidental scenario, retention of fission products in lead and/or migration in cover gas, retention in lead of Polonium isotopes and influence of a gas/steam trapping on its migration.
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European Lead Fast Reactor, Generation IV project (8) Experimental infrastructure Planning
HELENA-2 & ELF (2022-2025)
50 M€
Hands-ON (2024-2026)
Hub & Lead School (2023-2024)
2 M€
Meltin’Pot (2024-2026)
ALFRED (2035)
ATHENA & ChemLab 22 M€, In implementation 2020 2023
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FP7 / MAXSIMA Project Strategic Research Agenda of the EU Sustainable Nuclear Energy Technical platform requires new large infrastructures for its successful deployment. MYRRHA has been identified as a long term supporting research facility for all ESNII systems and as such put in the high-priority list of ESFRI. MAXSIMA (Methodology, Analysis and eXperiments for the "Safety In MYRRHA Assessment") aimed to contribute to the "safety in MYRRHA" assessment; 2012-2018 The project was coordinated by SCK•CEN Mol (Belgium), being carried out by a Consortium formed by 13 partners from Belgium, Italy, Kazakhstan, Germany, Netherlands, Romania, Spain and Sweden. Grant agreement ID: 323312
MAXSIMA work packages included: - safety analyses to support licensing of MYRRHA - detailed insight into the safety aspects of core components (fuel assemblies, and control and safety rod) - demonstration the level of safety of installing a steam generator into the primary pool, considering as basic scenario the rupture of a pressurized tube - test methodology development and validation for transient testing of MYRRHA type fuel, investigation of fuel-coolant and fuel-coolant-clad interactions and development of a conceptual design for an experiment related to severe accident analysis of MYRRHA type fuel in the IGR reactor at NNC (Kazakhstan) - development an enhanced innovative passive safety system Decay Heat Removal for HLM cooled reactors - evaluation of source terms for MYRRHA as well as a the containment analysis - education and training: workshops, lecture series, training sessions; virtual-safety simulator software was developed
RATEN ICN contribution aimed to develop and validate methodology and experimental devices for transient testing of MYRRHA type fuel segments in the ACPR-TRIGA Reactor. RATEN ICN acted also as work package leader for WP5 “Fuel safety”.
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IAEA Coordinated Research Projects
Coordinated Research Project (CRP) on “Reliability of High Power, Extended Burnup and Advanced PHWR Fuel” – code T12027; 2014-2018 IAEA - TECDOC - 1865 / 2019 CRP aims to pursue the following major research objectives: fuel design, nuclear fuel fabrication, irradiation and post-irradiation examinations of nuclear fuel (standard/ experimental) designated to be used in Advanced Pressure High Water Reactor (APHWR).
Activities carried out by RATEN ICN: - design of 43-element fuel bundle containing mixed oxide of thorium and uranium fuel (T43) - developing a version of the ROFEM code, to simulate the behavior of the T43 fuel bundle elements - performance analysis to assess the behavior of experimental fuel elements using the new version of ROFEM code ; - neutronic characterization of CANDU-Thorium fuel bundle (T43) - neutronic/3D diffusion assessment to establish the power histories for T43 fuel bundle behavior (DRAGON, DIREN codes); - fuel performance assessment of the behavior of the T43 fuel bundle/fuel elements - developing a manufacturing technology for mixed oxide of Th and U sintered pellets - manufacturing of an experimental fuel stack pellets with mixed oxide of Th and U (95% ThO2 and 5% enriched UO2 ) - irradiation of an experimental fuel element in TRIGA Research Reactor; - post-irradiation examination of the experimental fuel elements.
RATEN ICN was involved in the project "Development of a Fuel Bundle with 43 Elements Containing Mixed Oxide of Thorium and Uranium (T43) in ICN" Research Contract No. 18226
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IAEA INPRO Collaborative Projects and activities (1)
Task 1 - Global Scenarios Collaborative Projects (CPs)
SYNERGIES (Synergetic Nuclear Energy Regional Group Interactions Evaluated for Sustainability) CP; 2012-2015 final report IAEA Nuclear Energy Series NF-T-4.9 / 2018 Case study analyzing development of nuclear capacity and increasing of its share in the national energy mix in order to assure the sustainability, by considering regional collaborative architectures both in the front-end and back-end of nuclear fuel cycle
KIND (Key Indicators for Innovative Nuclear Energy Systems) CP; 2014-2017 final report IAEA Nuclear Energy Series NG-T-3.20 / 2019 Case study carrying out a multi-criteria comparative evaluation of evolutionary (GenIII+ enhanced CANDU technology) and innovative (GenIV LFR technology) NES technologies. KIND approach and KIND-ET tool with specific key indicators were applied. CANDU technology already operating in Romania was included, as reference, in the comparative analysis.
ROADMAPS ((Roadmaps for a Transition to Globally Sustainable Nuclear Energy ) CP; 2014-2018 final report content approved IAEA Nuclear Energy Series NG-T-3.22 Trial application of the ROADMAPS template to the national case study pursuing specific objectives: - preparation of structured information on NES development until 2100; - illustration of Romania’s NES development (security and needs for nuclear fuel supply, operation performance indicators, radioactive waste management, including waste disposal) and key developments to achieve a sustainable NES up to 2100; - identification of potential need for international collaborations in nuclear fuel cycle assuring benefits for national NES development
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IAEA INPRO Collaborative Projects and activities (2) Task 1 - Global Scenarios Collaborative Projects (CPs) and other activities
CENESO (Comparative Evaluation of Nuclear Energy System Options) CP; 2017- on-going Case study proposing to refine the multi-criteria comparative evaluation of innovative and evolutionary NES technologies carried out in the KIND CP framework from the perspective of associated Benefits and Challenges, using the KIND approach and the KIND-ET tool with new developed extensions.
ASENES Pilot Study on ″Sustainable Deployment Scenarios for Small Modular Reactors″; 2020 - on-going: Case study proposing to investigate development of SMRs in Romania in correlation with 5 scenarios resulting from the level of market penetration by vRES, the use of SMR or current commercial reactors, the use of current SMR technologies or those of Generation IV.
Develop and implement INPRO Task 1 Service to Member States; 2018 – 2020 final report content approved IAEA Nuclear Energy Series NG-T-3.21 - reviewing and updating lectures, exercises and materials for INPRO Service ASENES - developing lectures and writing materials based on the case studies performed in SYNERGIES, KIND and ROADMAPS CPs.
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IAEA INPRO Collaborative Projects and activities (3)
Task 3 - Sustainability Assessment and Strategies NESA Economics Support Tool (NEST) Update; 2017 – 2019
Task 4 – Dialogue and Outreach
Dialogue Forums on Global Nuclear Energy Sustainability; since 2012:
- advanced and innovative NES development, - updating and development of the INPRO Methodology, - analysis of drivers and impediments for regional cooperation towards sustainable NES, - assessment of nuclear energy potential to sustain the goals of sustainable development, considering reduction of climate changes effects
INPRO Training; since 2016: - instructor for modelling and assessment of NES using MESSAGE tool in regional trainings held in Morocco (2016), Poland and Romania (2017), - drafting the users guide for modelling of NES with MESSAGE, - performing a case study included in the report on Member States experience in modelling of NES with MESSAGE, - preparing training materials (lectures, practical exercises, sets of quizzes /answers for final examination) for the INPRO School
E-learning and distance learning tools to support INPRO Training; since 2019: - updating and improvement of training materials (lectures, practical exercises, sets of quizzes /answers for final examination) for the on-line training assisted by lecturers on the IAEA Learning Management System (LMS) platform. The materials were prepared for the experts from newcomer countries and included: Economics of nuclear energy; Modelling of NES; Comparative evaluation of NES options; Development of roadmaps for enhancing the nuclear energy sustainability
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EURATOM Projects (1)
Severe Accident Community objective: Experimental data, resulted from a huge effort, to be converted into valuable knowledge embedded into a performing computer code easy to simulate severe accident phenomena and produce source term.
PHEBEN, PHENEN2 (Collaborative projects on experiments, models and computer codes)
SARNET, SARNET2 (Construction and functioning of Network of Excellence)
CESAM (consolidation of models, extending the applicability, validation)
ASCOM ASTEC Community
Community of Practice
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EURATOM Projects (2) Severe Accident Community main outcomes : Excellent international collaboration creating the critical mass for a huge development ASTEC computer code with a detailed modelling of a large diversity of phenomena (core degradation, fission product transport, thermal-hydraulics, chemistry, molten core concrete interaction) ASTEC capability to simulate severe accidentys for all types of NPPs operating in Europe (PWR, VVER, BWR, CANDU) Extensive validation matrix (on international experiments, inter-comparison of codes)
Activities carried out by RATEN ICN: Coupling source-term calculation with dispersion modelling and emergency calculations (FASTNET project) Development of the methodology to simulate Spent Fuel Pool severe accidents Development of a broad spectrum of applications for all accidents RATEN ICN – CANDU modelling, specifications for the code development, validation efforts, plant application development (CANDU specificities for severe accidents) Excellent knowledge transfer between different groups, experts, formation of young researchers.
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EURATOM Projects (3)
European Network on Neutron Techniques Standardization for Structural Integrity (NeT)
Mission : to develop experimental and numerical techniques and standards for the reliable characterization of residual stresses in structural welds, as is an important part of assuring their short and long term structural performance.
NeT was established in 2002, and it has been operating since then on a "contribution in kind" basis from industrial, academic and research facility partners. NeT was founded and has been managed by the Laboratory for Neutron Scattering Methods at the High Flux reactor Unit of the Institute of Advanced materials of the Joint Research Centre of the European Commission. Nearly 30 organizations from Europe and beyond are currently contributing to the NeT activities.
Each problem examined by NeT is tackled by creating a dedicated Task Group (TG), which undertakes measurement and modelling round robin studies, and interpretation of their results. NeT has initiated 7 TGs on welding residual stress investigation. These are studying model cases of “simple” geometry welds applied on different nuclear grade structural materials, i.e. steels, Ni base alloys and Al alloys. In addition, NeT is running a TG on the application of Small Angle Neutron Scattering in order to obtain supplementary information on the materials under investigation at a (sub-) microscopic scale.
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EURATOM Projects (4)
European Network on Neutron Techniques Standardization for Structural Integrity (NeT) Activities carried out by RATEN ICN: - Numerical modelling of welding residual stress and distortions in TG1 (single bead-on-plate weldment), TG2 (letter box repair welds), TG4 (3-pass slot weld on stainless steel plate) and TG6 (3-pass slot weld on Ni alloy plate). - Sensitivity studies on the impact on predicted residual stress results of different modelling assumptions like: heat source model, material hardening model, thermal and mechanical boundary conditions aiming to both establish a best practice approach and to aid the overall modelling results analysis. - Analysis of welded specimens instrumented with thermocouples, in order to better assess the real thermocouple junction positions. Basing on the analysis results, an improved procedure was proposed for the preparation of additional specimens instrumented for thermal data acquisition. - Distortion measurements for one of the TG4 welded specimens by using a coordinate machine. - Material characterization activities for TG6, namely thermal analysis of base metal, in order to determine its specific physical properties (thermal conductivity, specific heat and density) required for the modelling round robin campaign. - Support for the design and implementation of the NeT website, www.net-network.eu.
RATEN ICN has been and is involved in various international projects and partnerships whose major objective is the development of nuclear energy. There were highlighted the RATE ICN specialists efforts in following directions: • development and implementation of innovative technologies (LFR technology,
construction of the ALFRED demonstrator) • access and acquisition of skills in working with calculation codes specific to the field; • experimental research and development activities in the field of nuclear materials
behavior; • design, testing, manufacture of standard and advanced nuclear fuel; research and
development in the phenomenology and management of severe accidents; • conducting case studies based on the national specifics of the nuclear energy system
applying methodologies and using modeling and evaluation tools available in international organizations;
• development and validation of safety design and evaluation tools, as well as qualification of materials for Advanced Generation IV reactors.
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Conclusions
THANK YOU FOR YOUR KIND ATTENTION and PATIENCE !
