Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis

被引：11

作者：

Ciurluini, C. ^{[1
]}

Narcisi, V ^{[1
]}

Tincani, A. ^{[2
]}

Ferrer, C. Ortiz ^{[3
]}

Giannetti, F. ^{[1
]}

机构：

[1] Sapienza Univ Rome, Dept Astronaut Elect & Energy Engn DIAEE, Rome, Italy

[2] ENEA FSN ING CR Brasimone, I-40032 Camugnano, BO, Italy

[3] ITER Org, F4E, Route Vinon Sur Verdon, F-13115 St Paul Les Durance, France

来源：

FUSION ENGINEERING AND DESIGN | 2021年 / 171卷

关键词：

ITER; TBM; WCS; RELAP5; LOHS;

D O I：

10.1016/j.fusengdes.2021.112598

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

In this paper, the conceptual design of the International Thermonuclear Experimental Reactor (ITER) WaterCooled Lithium-Lead (WCLL) Test Blanket Module (TBM) Water Cooling System (WCS) from Europe is presented. The system consists of two loops in series. This design feature allows the removal of heat from the TBM box avoiding at the same time the release of radionuclides into the ITER Component Cooling Water System (CCWS), that acts as WCLL Test Blanket System heat sink. For this purpose, the WCS primary loop deals with the direct heat removal from the ITER TBM and the secondary one implements physical separation between the contaminated primary loop coolant and the CCWS. The insertion of an economizer into the primary loop determines the characteristic "eight" shape of the circuit. This choice was done in order to reduce the temperature difference on the intermediate heat exchanger. Hairpin type and steam bubble are the technologies selected for heat exchangers and pressurizers, respectively. Pressure and temperature control systems are foreseen to limit excursions from rated values in normal operational states and abnormal transients. A computational activity was promoted to assess the WCLL-WCS conceptual design, using a modified version of the RELAP5 Mod3.3 system code. A detailed thermal-hydraulic model was developed on the basis of design outcomes. The nodalization scheme includes the TBM, the WCS, a portion of the CCWS and the lithium-lead circuit. The computational campaign involved both the normal operational state and selected abnormal transients. In all the scenarios simulated, the conceptual design has highlighted the capability of operating the system respecting all the thermal-hydraulic requirements. The abnormal transient selected and presented is the loss of flow in the CCWS (loss of heat sink). In these conditions, TBM cooling function has been verified, keeping standard control strategies without any external action.

引用

页数：13

共 30 条

[1] Updated design and integration of the ancillary circuits for the European Test Blanket Systems [J].

Aiello, A. ;

Arena, P. ;

Di Maio, P. A. ;

Ferrucci, B. ;

Forte, R. ;

Frisoni, M. ;

Galabert, J. ;

Ghidersa, B. E. ;

Granieri, M. ;

Ortiz, C. ;

Polidori, M. ;

Ricapito, I. ;

Tincani, A. ;

Tian, K. ;

Voukelatou, K. .

FUSION ENGINEERING AND DESIGN, 2019, 146 :27-30

[2]

ASME, 2015, BOIL PRESS VESS CO D

[3] Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER [J].

Aubert, J. ;

Aiello, G. ;

Alonso, D. ;

Batal, T. ;

Boullon, R. ;

Burles, S. ;

Cantone, B. ;

Cismondi, F. ;

Del Nevo, A. ;

Maqueda, L. ;

Morin, A. ;

Rodriguez, E. ;

Rueda, F. ;

Soldaini, M. ;

Vallory, J. .

FUSION ENGINEERING AND DESIGN, 2020, 160

[4] Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module [J].

Ciurluini, Cristiano ;

Giannetti, Fabio ;

Tincani, Amelia ;

Del Nevo, Alessandro ;

Caruso, Gianfranco ;

Ricapito, Italo ;

Cismondi, Fabio .

FUSION ENGINEERING AND DESIGN, 2020, 158

[5] Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project [J].

Del Nevo, A. ;

Arena, P. ;

Caruso, G. ;

Chiovaro, P. ;

Di Maio, P. A. ;

Eboli, M. ;

Edemetti, F. ;

Forgione, N. ;

Forte, R. ;

Froio, A. ;

Giannetti, F. ;

Di Gironimo, G. ;

Jiang, K. ;

Liu, S. ;

Moro, F. ;

Mozzillo, R. ;

Savoldi, L. ;

Tarallo, A. ;

Tarantino, M. ;

Tassone, A. ;

Utili, M. ;

Villari, R. ;

Zanino, R. ;

Martelli, E. .

FUSION ENGINEERING AND DESIGN, 2019, 146 :1805-1809

[6] An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort [J].

Federici, G. ;

Boccaccini, L. ;

Cismondi, F. ;

Gasparotto, M. ;

Poitevin, Y. ;

Ricapito, I. .

FUSION ENGINEERING AND DESIGN, 2019, 141 :30-42

[7] Overview of the ITER TBM Program [J].

Giancarli, L. M. ;

Abdou, M. ;

Campbell, D. J. ;

Chuyanov, V. A. ;

Ahn, M. Y. ;

Enoeda, M. ;

Pan, C. ;

Poitevin, Y. ;

Kumar, E. Rajendra ;

Ricapito, I. ;

Strebkov, Y. ;

Suzuki, S. ;

Wong, P. C. ;

Zmitko, M. .

FUSION ENGINEERING AND DESIGN, 2012, 87 (5-6) :395-402

[8] Overview of recent ITER TBM Program activities [J].

Giancarli, Luciano M. ;

Bravo, Xavier ;

Cho, Seungyon ;

Ferrari, Marco ;

Hayashi, Takumi ;

Kim, Byoung-Yoon ;

Leal-Pereira, Artur ;

Martins, Jean-Pierre ;

Merola, Mario ;

Pascal, Romain ;

Schneiderova, Iva ;

Sheng, Qian ;

Sircar, Amit ;

Strebkov, Yuri ;

van der Laan, Jaap ;

Ying, Alice .

FUSION ENGINEERING AND DESIGN, 2020, 158

[9]

Giannetti F., 2019, D1902ENBRT01 DIAEE S

[10]

Hernandez F.A., CONSOLIDATED DESIGN

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