Design of the integration interface between the EU HCPB TBM and the ITER TBM port plug including hot cell operations for connection
- 1. Forschungszentrum Karlsruhe (Germany). Euratom Association
- 2. ITER International Team-Cadarache Joint Work Site, Saint-Paul-lez-Durance (France)
Description
In the frame of the activities of the EU Breeder Blanket Programme and of the Test Blanket Working Group, the Helium Cooled Pebble Bed Test Blanket Module- (HCPB-TBM) System is developed. The TBM test schedule foresees four different campaigns for simulation of DEMO relevant conditions, campaign requires a dedicate TBM. Therefore a concept for TBM integration into ITER is designed with attention to simplify the mounting/dismounting operations. This paper presents the status of this concept with regard to the operations in hot cell required to install a new TBM into an equatorial TBM Port Plug (PP). This includes the establishment of the connection for the attachment, supply- and diagnostic lines in the environment of the interface (IF 1) between the TBM rear part and the PP backside shield. The connection of IF 1 has to be designed to cope with a temperature difference between TBM and PP (∝200 K) and the EM-loads during normal operation and disruption scenarios. The reference attachment concept based on shear keys and flexible cartridges is revised to cope with new conditions on the load and at the interface to the PP. According to the latest results of EM analysis, a radial component of the Maxwell forces (due to the ferromagnetic structural material) has been identified as an additional challenging load for the attachment. Furthermore, the replacing operations at IF 1 are influenced by the design of the PP; the recent ITER proposal based on a removable back side shield allows access to the IF 1 from the periphery after the frame of the PP surrounding the TBM is removed. As for the mechanical attachment, the tools and operations for connection of the TBM supply lines (Helium-, Purge- and measurement lines for different purpose depending on the test schedule) are strongly influenced by the restrictions to access IF 1, too. Dismantling of the frame would allow direct access to the interface by e.g. orbital welding tools. The concept for connection of the TBM diagnostic lines does not foresee an interface between the TBM and the PP back side shield because of the very restricted space conditions. Therefore the diagnostic lines will be routed inside of a pipe which is attached to the TBM rear part. This instrumentation pipe is designed to penetrate the whole radiation shield up to the interface between the PP back side shield rear part and the Ancillary Equipment Unit (AEU). At this interface the diagnostic lines exit the instrumentation pipe by a feed through where they are connected to a multi plug which provides the connection to the Data Acquisition System. The vacuum boundary between the back side shield and the instrumentation pipe will be provided by a bellow. After a consistent concept for the integration of the HCPB TBM in ITER has been developed, further investigation will be needed to develop tools and procedures which are required to install the TBM into the PP during the maintenance and refurbishment operations in the hot cell. (orig.)
Additional details
Publishing Information
- Imprint Title
- 8th international symposium on fusion nuclear technology (ISFNT-8). Proceedings
- Imprint Pagination
- 327 p.
- Journal Page Range
- [1 p.]
Conference
- Title
- 8. international symposium on fusion nuclear technology
- Acronym
- ISFNT-8
- Dates
- 30 Sep - 5 Oct 2007
- Place
- Heidelberg (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 39015616
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BREEDING BLANKETS; COOLING SYSTEMS; DATA ACQUISITION SYSTEMS; ELECTROMAGNETIC FIELDS; EQUIPMENT INTERFACES; FERROMAGNETIC MATERIALS; GAS COOLING; HELIUM; HOT CELLS; ITER TOKAMAK; MODULAR STRUCTURES; MONITORING; PIPES; SHIELDS; THERMONUCLEAR REACTOR MATERIALS; VACUUM SYSTEMS
- Descriptors DEC
- CLOSED PLASMA DEVICES; COOLING; ELEMENTS; ENERGY SYSTEMS; EQUIPMENT; FLUIDS; GASES; LABORATORY EQUIPMENT; MAGNETIC MATERIALS; MATERIALS; NONMETALS; RARE GASES; REACTOR COMPONENTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TUBES