[en] This article describes a method for testing of the efficiency of the biological shielding of the hot cell facility, which were constructed as a part of the project SUSEN. Ten hot cells and one semi-hot cell are present in the facility Radiochemistry II. The shielding is made from steel plates. In order to demonstrate sufficient efficiency of the biological shielding of the hot cells and a correspondence between measured and contractual values at selected points. The test was done using sealed high activity ⁶⁰Co sources. The results are also used as a proof of the optimization of radiation protection for the workplace of this type. The results confirm significant optimization of radiation protection at the workplace. The dose received by a staff do not exceed one tens of annual limit during active service. Obtained results fulfill general requirements of radiation protection and will be used for further active service of hot cells facility. - Highlights: • The efficiency of biological shielding of the hot cell facility is tested. • New removable hermetic box feature for use in hot cells is introduced. • Annual personal doses for staff of hot cells are calculated upon the dose rate measurements.

[en] In the Czech Republic irradiated fuel inspection has been carried out at Temelin NPP since 2003. Initial reason was the use of eastern reactor concept with western fuel type, then later confirmation of the new fuel from another manufacturer. Since 2008, Research Centre Rez Ltd. cooperates in inspections, whose team has been working as an independent check of the fuel supplier since 2011. Within post-radiation program the checks of the status of selected fuel assemblies are carried out during downtime on the block, i.e. visual inspection and measurement of torsion, bending and length of the fuel assembly takes place. (authors)

[en] In the Czech Republic irradiated fuel inspection has been carried out at Temelin NPP since 2003. Initial reason was the use of eastern reactor concept with western fuel type, then later confirmation of the new fuel from another manufacturer. Since 2008, Research Centre Rez Ltd. cooperates in inspections, whose team has been working as an independent check of the fuel supplier since 2011. Within post-radiation program the checks of the status of selected fuel assemblies are carried out during downtime on the block, i.e. visual inspection and measurement of torsion, bending and length of the fuel assembly takes place. (authors)

[en] This work is focused on the surveillance program for the life extension of the LVR-15 reactor. The flange for connection between the reactor vessel and horizontal canal, which ensures a connection between two different materials, and thus was chosen for investigation. The reactor vessel is made of stainless steel and the horizontal canal is made of aluminum. The identical flange was manufactured with the use of the same materials as the original one and has been irradiated in LVR-15 for 10 years till 2018. After that, the flange was transported to the hot cell facility, in January, 2019. The irradiation process simulates a life span of the original part. The dose equivalent rate of 40 mSv/h was measured on the surface after irradiation. Due to the mass of the flange of about 30 kg, it was necessary to prepare a detailed schedule of the manipulation. Since the manipulators maximum loading is only 5 kg, the handling with the flange was tricky and risky. This work describes handling, cutting, sample preparation and microstructure analysis of the highly irradiated flange in the hot cell facility. (author)

[en] This work is focused on specimens and infrastructure preparation for successful tensile, creep and strength relaxation tests on Zr cladding tube irradiated in the Czech nuclear power plant during normal operation. The results of these tests will be used as a material database for calculations and better understanding of cladding behavior under normal operation conditions

[en] The purpose of the paper is to present the hot cell facility which is being constructed as part of the project SUSEN at the Rez research center (Czech Republic). The Sustainable Energy Project (SUSEN) is implemented as a regional Research/Development center in Priority Axis 2 and its objective is to act as a relevant research partner for cooperation with other European research centers. The project is fully funded by the European Union. Within this project a new complex of 10 hot cells and one semi-hot cell will be built. There will be 8 gamma hot cells and 2 alpha hot cells. In each hot cell a hermetic, removable box made of stainless steel will home different type of devices. The hot cells and semi hot cell will be equipped with devices for processing samples (cutting, welding, drilling, machining) as well as equipment for testing (sample preparation area, stress testing machine, fatigue machine, electromechanical creep machine, high frequency resonance pulsator...) and equipment for studying material microstructure (micro-hardness and nano-hardness probes, scanning electron microscope). An autoclave with water loop, installed in a cell will allow mechanical testing in control environment of water, pressure and temperature. The transportation system for samples and materials is based on a mobile cask with an airtight connection and vertical access. The installation is designed to work with an activity level up to 300 TBq and to receive materials from decommissioned power reactors as well as highly irradiated materials for fusion applications

[en] This poster presents the hot cell facility which is being constructed as part of the SUSEN project at the Rez research center (Czech Republic). Within this project a new complex of 10 hot cells and one semi-hot cell will be built. There will be 8 gamma hot cells and 2 alpha hot cells. In each hot cell a hermetic, removable box made of stainless steel will home different type of devices. The hot cells and semi hot cell will be equipped with devices for processing samples (cutting, welding, drilling, machining) as well as equipment for testing (sample preparation area, stress testing machine, fatigue machine, electromechanical creep machine, high frequency resonance pulsator...) and equipment for studying material microstructure (nano-indenter with nano-scratch tester and scanning electron microscope). An autoclave with water loop, installed in a cell will allow mechanical testing in control environment of water, pressure and temperature. A scheme shows the equipment of each cell. This hot laboratory will be able to cover all the process to study radioactive materials: receiving the material, the preparation of the samples, mechanical testing and microstructure observation. Our hot cells will be close to the research nuclear reactor LVR-15 and new irradiation facility (high irradiation by cobalt source) is planned to be built within the SUSEN project

[en] The purpose of the poster is to present radiation protection and dosimetry in the new hot cell facility being constructed as part of the SUSEN project. The hot cell facility is composed of 10 hot cells and 1 semi-hot cell. All shielding is made from steel, the outer wall shielding has thickness of 500 mm, internal wall between hot cells 300 mm with the possibility to extension to 500 mm. The ceiling shielding has a thickness of 400 mm and the floor shielding is 300 mm wide. Shielded windows allow direct view into the hot cells. Their shielding effect is equivalent to 500 mm of steel. The dimension of the window in the control room is 800 mm x 600 mm with a thickness of 900 mm. All important operating data are collected in the central system of hot cells. The system monitors under-pressure level and temperature in each chamber. If necessary it can directly control the ventilation system. Each hot cell is equipped with dose rate probes. The system also measures and evaluates airborne radioactivity in the building

[en] A complex transmission electron microscopy (TEM) study of reactor vessel internal (RVI) materials from the baffle-former-barrel assembly from NPP Greifswald (VVER 440), Unit 1 decommissioned after 15 service cycles has been undertaken. All parts of the baffle-former-barrel assembly are made from Ti-stabilized austenitic stainless steel 08Ch18N10T. The materials were exposed to different dose of neutron radiation (2.4 - 11.4 dpa) at temperatures 267 - 398 deg. C depending on position in the core. Three types of radiation induced defects were identified and quantified, namely: dislocations, cavities (voids) and fine-scaled precipitated particles of Ni-Si rich phases. Black-dot type defects were observed too. Operation conditions are around ≅ 300 deg. C that is why we have observed defect typical for both low and high regions of irradiation temperatures. (authors)

[en] Highlights: → Doppler broadening (DB) of annihilation radiation was used as a novel technique for two dimensional mapping of lateral defect distribution in ultra fine grained Cu produced by high pressure torsion. → This paper introduces DB mapping and compares it with standard microhardness (HV) characterization. → DB mapping enables to visualize lateral distribution of dislocations and in particular deformation-induced vacancies which are invisible in HV mapping. → Hence, DB mapping can be considered as a complementary technique to standard HV characterization. -- Spatially resolved positron annihilation was employed for mapping lateral defect distribution in Cu deformed by high-pressure torsion. Parameters describing Doppler broadening of the annihilation peak were used for mapping the spatial distribution of defects. In comparison with microhardness showing a clear development towards homogeneity, positron annihilation revealed that spatial distribution of defects was far from uniform, even after 25 turns. This was mainly due to a higher concentration of deformation-induced vacancies at the periphery compared with the center.