Rapid Prototyping of Safety System for Nuclear Risks of the ITER Tokamak

被引:12
作者
Ambrosino, Giuseppe [1 ]
Banfi, Massimiliano [2 ]
Carannante, Giuseppe [1 ]
De Tommasi, Gianmaria [1 ]
Mandelli, Augusto [2 ]
Pironti, Alfredo [1 ]
Scibile, Luigi [3 ]
机构
[1] Univ Naples Federico 2, Assoc EURATOM ENEA CREATE, I-80125 Naples, Italy
[2] Natl Instruments Italy, I-20152 Milan, Italy
[3] ITER Org, F-90046 St Paul Les Durance, France
关键词
Hardware-in-the-loop (HIL) simulations; ITER; model-based design; rapid prototyping; PLASMA CONTROL; RELEVANT;
D O I
10.1109/TPS.2010.2049591
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The ITER tokamak (Latin for "the way") is the next step toward the realization of electricity-producing fusion power plants, since it has been designed to reach the plasma burning condition. The Central Safety System for Nuclear Risk (CSS) is the control system in charge to assure nuclear safety for the ITER plant, the personnel, and the environment. Since the CSS is a critical safety system, its validation and commissioning play an important role, and the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, mathematical models will help in the definition of the control system requirements. These models can be used for the rapid prototyping of the safety system, and hardware-in-the-loop (HIL) simulations can be performed to assess the performance of the control hardware against a plant simulator. This paper introduces the methodology and the software/hardware architecture used to develop both a CSS prototype and a ITER plant model suitable for the test and validation of this prototype.
引用
收藏
页码:1662 / 1669
页数:8
相关论文
共 16 条
[1]   The ITER design [J].
Aymar, R ;
Barabaschi, P ;
Shimomura, Y .
PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 (05) :519-565
[2]  
Cassandras C. G., 2009, INTRO DISCRETE EVENT, DOI DOI 10.1007/978-3-030-72274-6
[3]  
Chen F. F., 1974, Introduction to plasma physics
[4]   GRAFCET - A POWERFUL TOOL FOR SPECIFICATION OF LOGIC CONTROLLERS [J].
DAVID, R .
IEEE TRANSACTIONS ON CONTROL SYSTEMS TECHNOLOGY, 1995, 3 (03) :253-268
[5]  
DE TOMMASI G, 2007, IEEE T PLASMA SCI, V35, P709
[6]   The status of the ITER design [J].
Holtkamp, N. .
FUSION ENGINEERING AND DESIGN, 2009, 84 (2-6) :98-105
[7]   Development of ITER-relevant plasma control solutions at DIII-D [J].
Humphreys, D. A. ;
Ferron, J. R. ;
Bakhtiari, M. ;
Blair, J. A. ;
In, Y. ;
Jackson, G. L. ;
Jhang, H. ;
Johnson, R. D. ;
Kim, J. S. ;
LaHaye, R. J. ;
Leuer, J. A. ;
Penaflor, B. G. ;
Schuster, E. ;
Walker, M. L. ;
Wang, H. ;
Welander, A. S. ;
Whyte, D. G. .
NUCLEAR FUSION, 2007, 47 (08) :943-951
[8]   Plasma control systems relevant to ITER and fusion power plants [J].
Kurihara, K. ;
Lister, J. B. ;
Humphreys, D. A. ;
Ferron, J. R. ;
Treutterer, W. ;
Sartori, F. ;
Felton, R. ;
Bremond, S. ;
Moreau, P. .
FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) :959-970
[9]   Plasma control in ITER - "The way" to fusion energy [J].
Lister, JB ;
Portone, A ;
Gribov, Y .
IEEE CONTROL SYSTEMS MAGAZINE, 2006, 26 (02) :79-91
[10]  
*MATHW, 2009, STAT STAT COD 7 US G