Objetivo
Engineering support to the Next Step (NET/ITER)
Tests on mockups of components for Remote Handling and reliability analyses
Accident analyses of Next Step and power reactors
A twin-belt concept for attaching locks of plasma facing component has been developed. A design optimization process has been undertaken by considering different design parameters and additional constraints. Validation studies have been made on the electromechanical effects of plasma disruptions on plasma facing components. Different computational strategies have been developed and their application to plate models in bending modes have been performed. A small-size test-rig, ELBA, has been constructed.
The approach followed for the studies on remote assembly and maintenance of the future fusion reactors is based on computer simulation and experimental validation by using a facility named ROBERTINO, a large gantry robot with auxiliary equipments of the heavy robotics laboratory TELEMAC.
A CAD.CAE system allows the design of equipment and tools, identify the procedures and trajectories, and grphically simulate the operations required.
In parallel, ROBERTINO allows the validation of tools and procedures, taking into account particular consideration the safety critical hardware adn software aspects.
An appropriate control system has been developed as a safety critical computer system, in order to allow high precision and repeatability of positioning ensure the linking with the graphic simulation tool and the integration with a remote handling workstation.
The main results have been obtained for validating the vertical removal concept of blanket, by using one third scale mock ups of a vessel sector and the related blanket segments which are withdrawn and replaced through the upper access port. The results have allowed conditions for the feasibility of the concept to be defined.
Other imporant results have been aquired from tests of remote cutting and welding ofcoolant supply pipes by using boring tooling, with the indication of the critical issues to be solved.
Loss of offsite power, it was shown that the decay heat can cause potentially dangerous temperature peaks only several weeks after the accident, thus allowing corrective actions to be taken.
Loss of vacuum with air ingress into the plasma chamber was considered. The code SYFNOS describing the temperature histories in the various components and other relevant parameters (burnt graphite, expelled gases) was developed. As a results of the analysis it was found that this accident produces modest damages to the plant but high contamination levels may arise in some reactor rooms.
Neutron induced radioactivity effects on the lead lithium-17 breeder were studied. The topics investigated included: identification of the relevant short and long term radioisotopes, release fractions in accident conditions, effects of impurities, waste disposal and recyling aspects. It was shown that the radioactivity concerns on this alloy were overvalued in the past.
Progress to end 1991
- Twin-belt" concept for attaching locks of plasma-facing component.
A design optimization process has been undertaken by considering different design parameters and additional constraints.
- Validation studies on the Electromechanical effects of plasma disruptions on plasma facing components.
Different computational strategies have been developed and their application to plate models in bending modes have been performed. A small-size test-rig, ELBA, has been constructed. Remote Maintenance Operation (TELEMAC)
- Mockups of in-vessel components and test facilities, Task RHS3- 1 of the Tech. Prog. for NET.
The purpose of this activity is to validate the results of the computer simulation of the Remote Operation of in-vessel components on a 1/3 scale mockup. A facility named ROBERTINO, consisting of a gantry robot whose purpose is to extract and replace the blanket mock-up, has been set-up. A computer simulation package accepts design models of Remote Handling equipments and environment created using CAD and supports the assembly of the robot.
- Shielding Blanket Handling Device (BHD) Task RHI 1.2 of the Tech. Prog. for NET.
A first structural analysis of the inboard blanket segments has been carried out in support of the BHD design.
- Double lip seal joint design of cutting and welding tools, Task RHI 2-1 of the Tech.Prog. for NET.
The test results, the analysis of welding quality and the review of the tools design allow to consider the task properly concluded.
- Reliability Assessment of JET Robotics transporters.
The assessment regards the main crane communication system and the articulated boom. The failure mode analysis and its logical model have been completed. An impact analysis of the boom against one of its mechanical stops has been performed.
Accident analyses of NET-ITER (Task SEA 3 of the Techn. Progr. for NET)
- Loss of offsite power.
It was shown that the decay heat can cause potentially dangerous temperature peaks only several weeks after the accident, thus allowing corrective actions to be taken.
- Loss of vacuum with air ingress into the plasma chamber.
The code SYFNOS describing the temperature histories in the various components and other relevant parameters (burnt graphite, expelled gases) was developed. As a result of the analysis it was found that this accident produces modest damages to the plant but high contamination levels may arise in some reactor rooms.
Safety assessments of fusion power reactors (Tasks LTSE 1 and 2 of the Long Term Studies)
- Neutrons-induced radioactivity effects on Pb-17Li breeder.
The topics investigated included : identification of the relevant short- and long-term radioisotopes, release fractions in accident conditions, effects of impurities, waste disposal and recycling aspects. It was shown that the radioactivity concerns on this alloy were overevaluated in the past.
- Criteria for the definition of low activation materials.
A proposal has been made based on the compliance to short-and long-term radioactivity limits.
Detailed description of work foreseen in 1992 (expected results)
- NET Task on "Twin-belt" concept for attaching locks (AL) of PFCs.
The feasibility study will be pursued during 1992 in order to assess this concept as a reference solution. In parallel, other AL systems will be considered following the NET Team requests.
- Validation studies on the electromechanical effects of plasma disruptions on the PFCs.
The ELBA test-rig will be installed and the first experimental campaign will be carried out. The numerical validation will be pursued in collaboration with Electricite de France.
- Mockups of in-vessel components and test Facilities.
The development of an integrated software package including dynamic simulation, collision detection and avoidance, will be pursued. The proof of principle of the top loading of the plasma facing components on the 1/3 scale mockup of one sector of the NET/ITER Reactor, will be carried out, by using the ROBERTINO facility, for different attaching locks.
- Support for design of shielding Blanket Handling Device-BHD.
The ROBERTINO facility will be used for verifying the BHD design, in collaboration with ENEA. The reliability analysis of the system will be carried out.
- Reliability Assessment of JET Robotics Transporters.
The activities will be pursued on the analysis of Artificial Boom and initiated for the TARM system.
- NET/ITER Safety.
The work performed in 1991 on loss-of-cooling-capability accidents for the outboard zone of ITER will be extended for the whole machine.
- Long-Term safety.
The radioactivity issues for different options of structural and breeding materials will be assessed identifying the most suitable ones, for the different reactor zones. The low activation criteria developed during 1991 will be used as a reference for the materials in off-normal conditions.
Short description of evolution of work in 1993
- Involvement in joint operations for validation of computational methodologies with other Organisations and Industries.
- New validation tests on mockups in support to remote Handling system design of NET/ITER
- Quality Assurance of software packages developped for Remote Handling computer simulation.
- Accident analysis for ITER according to the design requests.
- First safety evaluations on the European fusion power reactor plant expected to be defined during 1992.
Ámbito científico (EuroSciVoc)
CORDIS clasifica los proyectos con EuroSciVoc, una taxonomía plurilingüe de ámbitos científicos, mediante un proceso semiautomático basado en técnicas de procesamiento del lenguaje natural. Véas: El vocabulario científico europeo..
CORDIS clasifica los proyectos con EuroSciVoc, una taxonomía plurilingüe de ámbitos científicos, mediante un proceso semiautomático basado en técnicas de procesamiento del lenguaje natural. Véas: El vocabulario científico europeo..
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Coordinador
21020 Ispra
Italia
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