[en] In 1998, in the frame of the European R and D on ITER high heat flux components, the fabrication of a full scale ITER Divertor Outboard mock-up was launched. It comprised a Cassette Body (CB), designed with some mechanical and hydraulic simplifications with respect to the reference body and its actively cooled Dummy Armour Prototype (DAP). This DAP consists of a Vertical Target (VT), a Wing (WI) and a Dump Target (DT), manufactured by European industries, which are integrated to the Gas Box Liner (GBL) supplied by the Russian Federation ITER Home Team. In 1999, in parallel with the manufacturing activity, the ITER European Home Team decided to assign to ENEA a Task for checking the component integration and performing the thermal-hydraulic and thermal mechanical testing of the DAP and CB. In 1999-2000, ENEA performed the experimental campaign at Brasimone Labs. The present work presents the experimental results of the component integration and the thermal-hydraulic and thermo-mechanical fatigue tests

[en] The year 2016 marks the fifth anniversary of the accident at the Fukushima Daiichi nuclear power plant and the 30th anniversary of the accident at the Chernobyl nuclear power plant. Research and know-how on remediation gained in the aftermath of these accidents has created a body of experience to support the recovery of agricultural production and rural development in the affected areas. Those countries that have been affected by such events have been working hard to remediate the situation and have gained valuable insights and experience. There is a need to promote and share this knowledge. This workshop, in particular, is promoting practical remediation activities. An appreciation of developments in this area will greatly improve emergency preparedness related to food and agricultural production.

[en] In 2001, EFDA has assigned to ENEA a contract for the thermomechanical testing of six mock-ups of the ITER primary wall module. These small scale mock-ups, reproducing representative portions of the reference ITER primary wall panels, were fabricated during ITER EDA phase by solid hot isostatic pressing (HIPping) of an AISI 316L stainless steel back structure to a alumina dispersion strengthened (DS)-Cu alloy heat sink armored with beryllium tiles. The experimental program, carried-out at ENEA Brasimone CEF 1-2 thermal hydraulic facility, was focused on the thermal mechanical testing of these mock-ups aiming at verifying which tile geometry and manufacturing procedure assures the required reliability of the beryllium/DS-Cu alloy/SS joints at high incident heat flux (>0.8 MW/m²) both at steady state and under thermal fatigue tests. The paper presents the progress in the experimental activity of the first test campaign and the main thermomechanical FEM analyses after the detachment and rupture of Beryllium tiles from one mock-up

[en] In 1998, in the frame of the ITER EDA phase, an European R and D Programme for the Blanket Design was implemented for developing and selecting the materials and the relevant fabrication procedures for manufacturing the shielding modules of the ITER Primary Wall. The fabrication of several Beryllium armored small scale mock-ups, reproducing representative portions of a Primary Wall panels, was also launched (Fusion Technol. (1998) 195). Further experimental activities were also programmed for investigating the thermal-mechanical behavior of these mock-ups at high heat flux and under thermal fatigue tests. In 2001, the ITER European Home Team decided to assign to ENEA a contract for the thermal fatigue testing of six mock-ups aiming at verifying the reliability of the Beryllium/Dispersion Strengthened Copper alloy/Stainless Steel and Beryllium/Precipitation hardened Copper alloy/Stainless Steel joints manufactured by solid Hot Isostatic Pressing (HIP) procedure (Technical Specification for the Thermal Fatigue Tests of Be protected EDA Mock-ups). The paper presents the results of the FEM thermal-mechanical analyses performed by ANSYS code and the progress of the first test campaign

[en] Full text: The medfly is a major pest for fruit crops worldwide and its presence in the countries means a threat for production and for export. The methodology that has been used in many countries to eradicate/suppress medfly population is the SIT (Sterile Insect Technique) that uses irradiation as a source for sterilisation. Besides medfly, Anastrepha species of quarantine relevance are important pests affecting the fruit crops in Brazil. Parasitoids that are natural enemies of fruit flies also will be reared in the facility for release in the production area. Finally, taking advantage of the large building area, the facility eventually will also produce sterile codling moths, a pest recently introduced into the south of Brazil and that affects the ever increasing apple and pear crops. The production of sterile medflies, natural enemies to control fruit flies and sterile codling moths - all of them using irradiation as sterilisation method and their release in the field is the most effective measure to control (suppression and eradication) such pests. The consumption of fresh fruits has increased worldwide and the production in Brazil either for domestic or export has been intensified in the last decade. As food safety is a major concern for the consumers, the use of environment-friendly technologies is always required. The SIT plays a major role for control fruit flies and other fruit pests. The final client for the sterile flies and moths will be the fruit growers in the tropical fruit growing areas in northern Brazil: Bahia, Pernambuco (Sao Francisco Valley), Ceara, north of Minas Gerais e north of Espirito Santo. Initially 200 million medflies and 10 million Diachasmimorpha longicaudata wasps will be released per week. The codling moths irradiated in the facility will be sent by air to the apple and stone fruit production areas in the south of Brazil, (Rio Grande do Sul and Santa Catarina), where the species is present. (author)

[en] HEXCALIBER was designed and manufactured to reproduce a portion of the former HCPB-TBM with two Lithium Orthosilicate and two Beryllium pebble bed cells both heated by couples of flat electrical heaters. The mock-up will be tested in HE-FUS 3 facility, under adequate adjustment of bed temperatures, temperature gradients, coolant temperatures, flow distributions and mechanical constraints, to assess the thermo-mechanical performance of the pebble beds under steady state and cyclic heat power conditions. The first test campaign is planned to be performed in the first part of 2007 using Lithium Orthosilicate (0.24-0.40 mm in diameter) pebbles as breeder material and Beryllium (1 mm in diameter) pebbles recently qualified as neutron multiplier. Among other experimental results, the temperatures, both in lithiated ceramics and Beryllium beds, and the overall displacements of the box will provide useful data to be compared with the theoretical ones computed by FEM codes with adequate models for pebble beds. The paper presents the main features of the HEXCALIBER mock-up, the detailed description of its experimental set-up and the first results of the experimental campaign. Moreover, the numerical simulation carried out by DIN on a 3D FEM model of HEXCALIBER, in the frame of the benchmark exercise, is also presented with details on the mock-up and cooling system nodalization and adopted loads and boundary conditions. Finally, the most significant numerical results, concerning temperatures and displacements at the instrumented points of the mock-up, are critically compared with the relevant measured values. (orig.)

[en] In the frame of the activities related to ITER divertor R and D, ENEA CR Brasimone was charged by EFDA (European Fusion Design Agreement) to investigate the thermal-hydraulic behaviour of the full-scale divertor plasma facing components, i.e. Inner Vertical Target, Dome Liner and Outer Vertical Target, both in steady state and during draining and drying transient. More in detail, for each PFC, the first phase of the work is the steady state hydraulic characterization which consists of: - measurements of pressure drops at different temperatures; - determination of the velocity distribution in the internal channels; - check the possible insurgence of cavitation. The subsequent phase of the thermal-hydraulic characterization foresees a testing campaign of draining and drying procedure by means of a suitable gas flow. The objective of this experimental procedure is to eliminate in the most efficient way the residual amount of water after gravity discharge. In order to accomplish this experimental campaign a significant modification of CEF1 loop has been designed and realized. This paper presents, first of all, the experimental set-up, the agreed test matrix and the achieved results for both steady state and transient tests. Moreover, the level of the implementation of a predictive hydraulic model, based on RELAP 5 code, as well as its results are described, discussed and compared with the experimental ones. (orig.)

[en] Highlights: • A dedicated facility, called TRIEX was manufactured in order to investigate the tritium extraction efficiency of GLC as TEU (Tritium Extraction Unit) of HCLL-TBM. • The experimental characterization of GLC has been performed in view of its utilization for the TES (Tritium Extraction System) of ITER. • An analytical model has been developed in this paper. • Results of experimental measurement of the parameters such as tritium extraction efficiency have been analyzed and compared with literature data. • It turns out the Tritium extraction value in the range between 10- and 30%. - Abstract: One of the main open issues in the design of the HCLL Test Blanket System for nuclear fusion energy applications is the design and testing of the Tritium Extraction Unit (TEU). The lead-lithium alloy which, in the HCLL blanket project, is used both as tritium breeder and neutron multiplier, will generate tritium that must be extracted with an efficiency as high as possible in order to keep low the tritium concentration in the liquid metal, then minimizing tritium permeation into the main coolant, the consequent CPS load and, last but not least, tritium permeation into the Port Cell through the PbLi loop pipes. Gas-liquid contactors (GLC) and, more in detail, packed columns are the reference technology for TEU of European ITER HCLL-TBS. An experimental campaign on a GCL packed column was performed in TRIEX (TRItium Extraction) facility in ENEA Brasimone Research Centre. Starting from the experimental results a parametric analysis was performed in order determine the basic parameters of the gas extraction process and consequently the efficiency of this technology in different operative conditions. Experiments were conducted at a constant temperature of 450 °C varying the mass flow rate in the range 0,1–0,35 kg/s for lead lithium and 5–150 Nl/h for Ar stripping gas. The hydrogen partial pressure in lead lithium at extractor inlet was investigated in the range between 8.000–14.300 Pa. The experimental results have shown a tritium extraction efficiency in the range between 10 and 30% in good agreement with past experimental results obtained in MELODIE loop in CEA using similar packing material.

[en] Highlights: ► The HETS (high-efficiency thermal shield) concept, initially developed by ENEA for water, has been adapted for use with He as coolant. ► This DEMO divertor concept is based on elements joined in series and protected by a hemispheric dome. ► It has been calculated to be capable of sustaining an incident heat flux of 10 MW/m² when operating at 10 MPa, an inlet He temperature of 600 °C, and an outlet temperature of 800 °C. ► The activity is focused on the manufacturing of a single HETS module with W armor and on its thermal–hydraulic testing. ► A CFD analysis by ANSYS-CFX was performed in order to predict the thermal–mechanical behavior of the module and a final comparison with the experimental data is required to validate the CFD results. - Abstract: The development of a divertor concept for fusion power plants that is able to grant efficient recovery and conversion of the considerable fraction (∼15%) of the total fusion thermal power incident is deemed to be an urgent task to meet in the EU Fast Track scenario. The He-cooled conceptual divertor design is one of the possible candidates. Helium cooling offers several advantages including chemical and neutronic inertness and the ability to operate at higher temperatures and lower pressures than those required for water cooling. The HETS (high-efficiency thermal shield) concept, initially developed by ENEA for water, has been adapted for use with He as coolant. This DEMO divertor concept is based on elements joined in series and protected by a hemispheric dome; it allows an increase of thermal exchange coefficient both for high speed of gas and for “jet impingement” effects of gas coming out from the internal side of hemispheric dome. It has been calculated to be capable of sustaining an incident heat flux of 10 MW/m² when operating at 10 MPa, an inlet He temperature of 600 °C, and an outlet temperature of 800 °C. The presented activity, performed in the frame of EFDA-TW5TRP-001 task, was focused on the manufacturing of a single HETS module and on its thermal–hydraulic testing. The materials used for the HETS module manufacturing were all DEMO-compatible: W for the armor material and the hemispherical-dome, DENSIMET for the exchanger body. The testing is performed by connecting the module to HEFUS3 He loop system that is a facility able to supply the He flow to the required testing conditions: 400 °C, 4–8 MPa and 20–40 g/s. The needed incident heat flux is obtained by RF inducting equipment coupled to an inductor coil installed just over the HETS module. A CFD analysis by ANSYS-CFX was performed in order to predict the thermal–mechanical behavior of the module and a final comparison with the experimental data is required to validate the CFD results. All parameters are monitored and recorded by data acquisition system.

No abstract available