Shuff R.,United Technologies |
Locke D.,Fusion for Energy F4E |
Roulet D.,Comex Nucleaire
Fusion Engineering and Design | Year: 2011
This paper reports on the use of Discrete Event Simulation tools for operability analysis of the Iter Hot Cell (HC) design. A simulation model representing the operation of the ITER Hot Cell has been created. The model incorporates the process logic for ITER components that are required to be refurbished, maintained and disposed of within the Hot Cell. This paper presents some results of the simulation indicating the performance of the Hot Cell for Divertor and Port Plug refurbishment. The results show that based on the established task durations a full 54 cassette Divertor refurbishment takes 4536 h, longer than the planned 6-month shutdown scheduled for the task. The simulation provides a platform to accurately size the capacity of process equipment with respect to given budgetary constraints and to identify opportunities to smooth the process flow. Effects of parameters such as human resource shift patterns, equipment mean time between failure and random variability in process times on overall Hot Cell productivity have been studied. The simulation model is flexible, capable of evolving in parallel with the Hot Cell design as more detailed input data becomes available thereby providing a valuable decision making and design optimisation tool throughout the development of the Hot Cell and beyond that into operation. © 2011 Published by Elsevier B.V.
Abonneau E.,CEA |
Le Coz P.,CEA |
Settimo D.,EdF |
Hamy J.-M.,AREVA |
And 8 more authors.
International Congress on Advances in Nuclear Power Plants, ICAPP 2014 | Year: 2014
The Preconceptual Design phase (AVP1) of the ASTRID project started in 2010 and ended in late 2012. During this phase, the aim of the ASTRID project is to integrate innovative options to meet the objectives of the 4th generation reactors and comply with the related specifications. Therefore, ASTRID project is based on a significant research and development program started in 2006 with EDF and AREVA to supply the necessary elements for the qualification of the ASTRID options in due time. Option Selection Processes (RCOs) were performed during the AVP1 phase and were structuring stages to compare several options studied. RCOs were mainly scheduled for 2012 and the last ones during the first part of 2013. RCOs make it possible to determine, among the technical solutions left open at the time when the AVP1 was launched, the reference technical option for the conceptual phase studies (AVP2, from 2013 till the end of 2015) and, if applicable, to keep a backup alternative or an advanced solution. Main results of choices made in 2013 are presented in this paper. Cost reduction phase was mastered in order to reduce the overall project cost and establish a new configuration of the ASTRID plant. In the meantime, the Safety Orientation Report (DOrS) was issued and discussed with the Nuclear Safety authority (ASN). These two points are also developed in this paper.
Giancarli L.M.,ITER Organization |
Cortes P.,ITER Organization |
Iseli M.,ITER Organization |
Lepetit L.,ITER Organization |
And 7 more authors.
Fusion Engineering and Design | Year: 2014
Three ITER equatorial port cells are dedicated to the assessment of six different designs of breeding blankets, known as Test Blanket Modules (TBMs). Several high temperature components and pipework will be present in each TBM port cell and will release a significant quantity of heat that has to be extracted in order to avoid the ambient air and concrete wall temperatures to exceed allowable limits. Moreover, from these components and pipes, a fraction of the contained tritium permeates and/or leaks into the port cell. This paper describes the optimization of the heat extraction management during operation, and the tritium concentration control required for entry into the port cell to proceed with the required maintenance operations after the plasma shutdown. © 2014 L.M. Giancarli.
Van der Laan J.G.,ITER Organization |
Cuquel B.,Airbus |
Demange D.,Karlsruhe Institute of Technology |
Ghidersa B.-E.,Karlsruhe Institute of Technology |
And 6 more authors.
Fusion Engineering and Design | Year: 2015
This paper describes the main acceptance criteria and required acceptance tests for the components of the six Test Blanket Systems to be installed and operated in ITER. It summarizes the guide-line toward the establishment of detailed test plans for the TBS, starting from the end-product at the ITER Members factories, and to generally define the type of tests that have to be performed on the ITER site after shipment, and/or prior to the systems final commissioning phase. © 2015.
Kim B.-Y.,ITER Organization |
Marconi M.,LTCalcoli |
Neviere J.-C.,Comex Nucleaire |
Merola M.,ITER Organization |
And 3 more authors.
Fusion Engineering and Design | Year: 2015
In three of the ITER equatorial ports, tritium breeding blanket concepts will be validated and tested using mock-up breeding blankets called test blanket modules (TBM). In these ports, two TBM-Sets are mechanically attached in a TBM Frame to form a TBM port plug (TBM PP). The ITER Organization is responsible for the design and manufacture of both this TBM Frame and the Dummy TBMs which will fill them. As a part of this development, in 2013, a conceptual design review (CDR) of TBM PP with two dummy TBMs revealed the need for improvement of design performance, interfaces and maintainability. This paper presents the main design improvements after the CDR as well as associated feasibility analysis of the improved design focusing on the attachment. Finally the work plan for the Preliminary Design phase is summarized. © 2015 Elsevier B.V.