News from ETSON and its members*
|30 Aug 2021 | SEC NRS |||Registration by Rospatent of the Computer Code "Calculator of Radiation and Thermophysical Characteristics of Spent Nuclear Fuel (v2.0)" and the Database "Database for Radiation and Thermophysical Characteristics of Spent Nuclear Fuel (v2.0)"
The Computer Code "Calculator of Radiation and Thermophysical Characteristics of Spent Nuclear Fuel (v2.0)" was introduced into the Registry of Computer Codes under the registry No. 2021617328 dated of 13.05.2021.
|22 Jul 2021 | LEI |||Women in Fusion Event during FEC2020 provides honest views and concrete proposals to improve gender equity in fusion
Women in Fusion Side Event, was held on Wednesday 12 May during the IAEA FEC2020 virtual conference. A group of women panellists, ranging from the highly experienced to newly coined PhDs, discussed the challenges of having a successful career in nuclear physics and nuclear engineering, a mainly male-dominated field.
|22 Jul 2021 | LEI |||International cooperation in the development of models for severe accident analysis in VVER-1000
To assist the State Nuclear Regulatory Inspectorate of Ukraine (SNRIU) in preparation of means for Severe Accident Management Guidelines (SAMG) validation the project financed by the European Commission through the Instrument for Nuclear Safety Cooperation (INSC) Action Programme 2015 has been performed in 2017 – 2021 by an international project team led by LEI. The main goal was the development and validation of VVER-1000 models for Ukrainian NPP using MELCOR code by Ukrainian technical support organisation.
|22 Jul 2021 | LEI |||Preparation of young generation nuclear energy specialists at LEI
Two research topics for PhD related to spent nuclear fuel management were announced in 2021. Collaborative doctoral partnership is developed among Kaunas University of Technology, Lithuanian Energy Institute and the Joint Research Centre of the European Commission. Within the frame of such collaboration, the researchers of LEI, JRC center in Karlsruhe (Germany) and Institute for Transuranium Elements are performing in cooperation an integral analysis of the process inside the fuel rods during accidents.
|22 Jul 2021 | Bel V |||UMAN – Towards a common understanding of uncertainty management in radioactive waste management
The main objectives of the Uncertainty Management multi-Actor Network (UMAN) are to provide an opportunity to different actors of EU Member States involved in radioactive waste management programmes to share their experiences and views on uncertainty management and to identify emerging needs that could be addressed in subsequent waves of the European Joint Programme on Radioactive Waste Management (EURAD).
|22 Jul 2021 | Bel V |||Surface specific clearance levels based on the Sudoqu methodology
For many years, even decades, there have been endless discussions on what values to use when performing clearance based on surface specific measurements. The definition of contamination in the Transport Regulation by IAEA and an old study by Fairbairn, gave rise to the numbers 0.04 Bq/cm2 for radiotoxic alpha-emitters and 0.4 Bq/cm2 for beta/gamma emitters. These values are widely used, but also often contested and challenged. Only a thorough, comprehensive study on the derivation of nuclide specific surface clearance levels can give a founded answer to the raised issues.
|22 Jul 2021 | Bel V |||Fire R&D Activities in Belgium
Historically, the first fire protection regulations to be implemented could be described as prescriptive (or deterministic), where the performance requirements of fire protection equipment are fixed. An example of such requirement is the need to segregate Structures, Systems & Components (SSCs) important for safety with fire-rated barriers ensuring standard resistance to fire propagation between compartments (e.g. for 3 hours according to U.S. NRC regulations). Such ratings are based on standardized testing procedures (ASTM, NFPA, EN...) performed under defined conditions (like the ISO 834 time-temperature curve).
|22 Jul 2021 | ETSON |||Improving Modeling Accuracy and Interpretation Skills Within ETSON EP&R Community
The consequences of the radiological and nuclear emergencies may vary from an overexposure of a single person to a transboundary catastrophe with multiple victims and massive radiation contamination. In light of the effort and resources potentially involved in the mitigation, assessment of the radiological consequences during an emergency is a vital stage in the planning and response.
|22 Jun 2021 | VTT |||VTT is developing reactor technology for district heating
In February 2020, a project was launched at VTT to develop a nuclear district heating plant for the Finnish market. The developed technology is called the Low-Temperature District Heating and Desalination Rector, or LDR.
|22 Jun 2021 | VTT |||Finnish Nuclear Research Programme Status (KYT2022 and SAFIR2022)
Finland has two ongoing national research programmes in the nuclear sector: KYT2022 and SAFIR2022. The two research programmes held a joint Interim Seminar in March.
|22 Jun 2021 | VTT |||Unreliability of reactor water level measurement during a severe accident
The reactor water level measurement became unreliable during the Fukushima accident. VTT has analyzed the behavior of the measurement system at unit 2.
|22 Jun 2021 | RATEN ICN |||Stepping forward for ALFRED infrastructure
ALFRED infrastructure was designed as a Research Infrastructure of global relevance on the HLM and LFR technology.
|22 Jun 2021 | RATEN ICN |||Evaluation of Advanced Nuclear Fuel Elements Behaviour Proposed for Use in CANDU Nuclear Reactor
Different concepts for nuclear heavy water reactors fuel bundles were compared and analysed from the thermo-mechanical point of view by using specific computer codes.
|22 Jun 2021 | EK CER |||EK-CER is a Collaborating Centre of the IAEA in Nuclear Forensics
Centre for Energy Research (EK) in Budapest, Hungary was designated as the first Collaborating Centre in Nuclear Forensics of the IAEA in 2016 which was prolonged this year till 2025. The Centre provides laboratory, research and training capacity, expertise, and mentoring opportunities together with scientific collaborations in the field of nuclear security.
|17 May 2021 | JSI |||THELMA laboratory at the JSI
Accurate prediction of the convective single- and two-phase heat transfer is very important in process and power engineering for safety, reliability, and efficiency. In this aspect, boiling is particularly interesting and complex phenomena, which may significantly enhance the heat transfer from the heated surface to the coolant flow. The detailed understanding of these phenomena is of great importance and, as such, is put under investigation in the THELMA laboratory (Thermal-Hydraulics Experimental Laboratory for Multiphase Applications) at the Reactor Engineering Division at Jožef Stefan Institute (Slovenia).
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