Assessment of the relevancy of ENEA Water Loop facility with respect to ITER WCLL TBS Water Cooling System by considering their thermal-hydraulic performances

被引:1
|
作者
Gonfiotti, B. [1 ]
Ciurluini, C. [2 ]
Giannetti, F. [2 ]
Arena, P. [1 ]
Del Nevo, A. [1 ]
机构
[1] ENEA, Dept Fus & Nucl Safety Technol, I-40032 Camugnano, BO, Italy
[2] Sapienza Univ Rome, DIAEE Dept, I-00186 Rome, Italy
关键词
Water Loop; WCLL-WCS; RELAP5; Normal operational state; LOFA;
D O I
10.1016/j.fusengdes.2024.114375
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
The Water -Cooled Lead -Lithium (WCLL) is one of the two candidate concepts for the Breeding Blanket (BB) of DEMO. A Test Blanket Module (TBM) together with its Water Cooling System (WCS) is going to be installed and tested in the ITER reactor. The WCS acts as primary cooling circuit of the TBM module, and it is designed to reproduce the water thermodynamic conditions expected at the DEMO BB inlet. During last years, ENEA and the DIAEE of Sapienza University of Rome have carried out the conceptualization of the Water Loop (WL) facility, belonging to the W -HYDRA experimental platform planned at C.R. Brasimone. The W -HYDRA platform is composed by three individual facilities called: Water Loop, Steam, and LIFUS5/Mod4. Water Loop replicates the salient thermal -hydraulic features of the ITER WCLL WCS, and it is equipped with a test section placed inside a Vacuum Vessel (VV) to investigate mock-ups of the whole TBM or its individual parts. This paper assesses the relevancy of the WL facility with respect to ITER WCLL TBM System comparing their thermal -hydraulic performances during selected operational and accidental conditions. Two RELAP5/Mod3.3 models were developed, and the outcomes of the simulations showed a good agreement, thus demonstrating the effectiveness of WL facility to support the ITER TBM program.
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页数:7
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  • [1] Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis
    Ciurluini, C.
    Narcisi, V
    Tincani, A.
    Ferrer, C. Ortiz
    Giannetti, F.
    [J]. FUSION ENGINEERING AND DESIGN, 2021, 171
  • [2] Thermal-Hydraulic Analysis of ITER Component Cooling Water System Loop 2B
    Guo, Bin
    Dell'Orco, Giovanni
    Liliana, Teodoros
    Steve, Ployhar
    Tao, Jun
    Fu, Peng
    Yang, Lei
    Kumar, Ajith
    Gupta, Dinesh
    Patelkumar, Nirav
    Jadhav, Mahesh
    [J]. JOURNAL OF FUSION ENERGY, 2016, 35 (02) : 335 - 340
  • [3] Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module
    Ciurluini, Cristiano
    Giannetti, Fabio
    Tincani, Amelia
    Del Nevo, Alessandro
    Caruso, Gianfranco
    Ricapito, Italo
    Cismondi, Fabio
    [J]. FUSION ENGINEERING AND DESIGN, 2020, 158
  • [4] PACTITER-OSCAR comparison in ACPs determination for the ITER WCLL-TBS Water Cooling System
    Mariano, G.
    Colangeli, A.
    Flammini, D.
    Fonnesu, N.
    Moro, F.
    Noce, S.
    Ortiz, C.
    Spagnuolo, G. A.
    Terranova, N.
    Villari, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2023, 191
  • [5] Thermal–Hydraulic Analysis of ITER Component Cooling Water System Loop 2B
    Bin Guo
    Giovanni Dell’Orco
    Teodoros Liliana
    Ployhar Steve
    Jun Tao
    Peng Fu
    Lei Yang
    Ajith Kumar
    Dinesh Gupta
    Nirav Patelkumar
    Mahesh Jadhav
    [J]. Journal of Fusion Energy, 2016, 35 : 335 - 340
  • [6] Thermal hydraulic transient analysis of ITER safety-relevant secondary cooling water system
    Vicini, Lavinia
    Schiliuk, Nicolas
    Coscarelli, Eugenio
    Dell'Orco, Giovanni
    Narcisi, Vincenzo
    Caruso, Gianfranco
    [J]. FUSION ENGINEERING AND DESIGN, 2021, 165
  • [7] THERMAL-HYDRAULIC CHARACTERISTICS AND HEAT REMOVAL CAPABILITY OF CONTAINMENT COOLING SYSTEM WITH EXTERNAL WATER WALL
    KATAOKA, Y
    FUKUI, T
    HATAMIYA, S
    MURASE, M
    NAITOH, M
    SUMIDA, I
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1990, 27 (09) : 802 - 814
  • [8] Thermal behaviour analysis on ITER component cooling water system loop 2B
    Guo, Bin
    Fu, Peng
    Dell'Orco, Giovanni
    Liliana, Teodoros
    Tao, Jun
    Yang, Lei
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 100 : 249 - 253
  • [9] Thermal-hydraulic assessment of Once-Through Steam Generators for EU-DEMO WCLL Breeding Blanket primary cooling system application
    Ciurluini, C.
    Vannoni, Alessandra
    Del Moro, Tommaso
    Lorusso, Pierdomenico
    Tincani, Amelia
    Del Nevo, Alessandro
    Barucca, Luciana
    Giannetti, Fabio
    [J]. FUSION ENGINEERING AND DESIGN, 2023, 193
  • [10] Transient System Thermal-Hydraulic Assessment of Advanced Uranium- and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors-II: Full-Core Analyses
    Wang, S.
    Beuthe, T.
    Huang, X.
    Dominguez, A. Nava
    Bromley, B. P.
    Colton, A., V
    [J]. NUCLEAR TECHNOLOGY, 2021, 207 (04) : 494 - 520