|28 Dec 2022||Practical example of application of an Integrated Safety Approach (ISA): NSRD of the post-operational phase of the Belgian NPPs
In order to establish the Nuclear Safety Requirements Document (NSRD) for the post-operational phase (POP) of the Belgian NPPs, the licensee (Electrabel) applied an efficient Integrated Safety Approach (ISA) based on Bel V recommandations.
|31 Jan 2022||Preparation of the post-operational phase of the Belgian NPPs
Bel V is currently actively working on the preparation of the post-operational phase of the life of the Belgian NPPs. This phase directly follows the definitive shutdown and aims in a time period of approximately 5 years at evacuating the spent fuels and the operational waste from the units, and at preparing the dismantling activities.
|22 Jul 2021||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||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||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).
|15 Feb 2021||The SF² project, for a safe interim storage of spent fuel
There is a need for the construction of supplementary interim storage capacity for spent fuel in Belgium, because of the definitive shutdown of the 7 nuclear power plants in the next 4 years.
|15 Feb 2021||Bel V participated in the installation of a new experiment in the IRSN Underground Research Laboratory at Tournemire
There is a need for the construction of supplementary interim storage capacity for spent fuel in Belgium, because of the definitive shutdown of the 7 nuclear power plants in the next 4 years
|15 Feb 2021||Experimental and numerical assessment of Natural Circulation Interruption phenomena
In the framework of the OECD/NEA PKL projects , Bel V proposed to perform a series of experimental tests connected with the Natural Circulation Interruption (NCI) issue. The objective was to assess the natural circulation interruption phenomena under asymmetric cooldown conditions and its eventual impact on the current operating emergency procedures (EOPs).
|16 Sep 2020||The MYRRHA Project, an innovative Lead-Bismuth cooled reactor
MYRRHA (Multipurpose hYbrid Research Reactor for High-tec Applications) is a unique highly innovative prototype of a nuclear reactor driven by a high power linear accelerator. It will be designed to operate in both critical (no accelerator needed) and subcritical mode. MYRRHA has a fast spectrum core cooled by Lead Bismuth Eutectic (LBE).
|16 Sep 2020||Thermal Fatigue issue in the Upper Plenum Injection lines at Doel 1-2
A leak suspected to have been caused by high cycle thermal fatigue due to fluctuating axial motion of a swirl penetration front end has been detected in early 2018 in a non-isolable Reactor Coolant System branch at the Doel 1 Nuclear Power Plant (Belgium).
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