Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components

Giuseppe Vella, Pietro Alessandro Di Maio, Tincani, Dell'Orco, Ricapito, Riccardi

Risultato della ricerca: Article

7 Citazioni (Scopus)

Abstract

In the frame of the activities related to ITER divertor R&D, ENEA CR Brasimone was in charge by EFDA (European Fusion Development Agreement) to investigate the thermal-hydraulic behaviour of the fullscale divertor plasma facing components, i.e. the outer vertical target, the inner vertical target and the dome-liner, both in steady state and during draining and drying transient. The investigation was performed by means of both experimental test campaigns performed at ENEA CR Brasimone and theoretical simulation developed in RELAP5 Mod.3.3 environment at the Department of Nuclear Engineering of the University of Palermo (DIN). This paper presents the achieved experimental results for both steady state and transient tests. Moreover, the level of the implementation of the predictive hydraulic model, based on RELAP5 code, as well as its results are described, discussed and compared with the experimental ones.
Lingua originaleEnglish
pagine (da-a)1034-1037
Numero di pagine4
RivistaFusion Engineering and Design
Volume83
Stato di pubblicazionePublished - 2008

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Hydraulics
Nuclear engineering
Plasmas
Hydraulic models
Domes
Drying
Fusion reactions
Hot Temperature

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Cita questo

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title = "Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components",
abstract = "In the frame of the activities related to ITER divertor R&D, ENEA CR Brasimone was in charge by EFDA (European Fusion Development Agreement) to investigate the thermal-hydraulic behaviour of the fullscale divertor plasma facing components, i.e. the outer vertical target, the inner vertical target and the dome-liner, both in steady state and during draining and drying transient. The investigation was performed by means of both experimental test campaigns performed at ENEA CR Brasimone and theoretical simulation developed in RELAP5 Mod.3.3 environment at the Department of Nuclear Engineering of the University of Palermo (DIN). This paper presents the achieved experimental results for both steady state and transient tests. Moreover, the level of the implementation of the predictive hydraulic model, based on RELAP5 code, as well as its results are described, discussed and compared with the experimental ones.",
keywords = "DIVERTORE, FUSIONE NUCLEARE, ITER, TERMOIDRAULICA",
author = "Giuseppe Vella and {Di Maio}, {Pietro Alessandro} and Tincani and Dell'Orco and Ricapito and Riccardi",
year = "2008",
language = "English",
volume = "83",
pages = "1034--1037",
journal = "Fusion Engineering and Design",
issn = "0920-3796",
publisher = "Elsevier BV",

}

TY - JOUR

T1 - Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components

AU - Vella, Giuseppe

AU - Di Maio, Pietro Alessandro

AU - Tincani, null

AU - Dell'Orco, null

AU - Ricapito, null

AU - Riccardi, null

PY - 2008

Y1 - 2008

N2 - In the frame of the activities related to ITER divertor R&D, ENEA CR Brasimone was in charge by EFDA (European Fusion Development Agreement) to investigate the thermal-hydraulic behaviour of the fullscale divertor plasma facing components, i.e. the outer vertical target, the inner vertical target and the dome-liner, both in steady state and during draining and drying transient. The investigation was performed by means of both experimental test campaigns performed at ENEA CR Brasimone and theoretical simulation developed in RELAP5 Mod.3.3 environment at the Department of Nuclear Engineering of the University of Palermo (DIN). This paper presents the achieved experimental results for both steady state and transient tests. Moreover, the level of the implementation of the predictive hydraulic model, based on RELAP5 code, as well as its results are described, discussed and compared with the experimental ones.

AB - In the frame of the activities related to ITER divertor R&D, ENEA CR Brasimone was in charge by EFDA (European Fusion Development Agreement) to investigate the thermal-hydraulic behaviour of the fullscale divertor plasma facing components, i.e. the outer vertical target, the inner vertical target and the dome-liner, both in steady state and during draining and drying transient. The investigation was performed by means of both experimental test campaigns performed at ENEA CR Brasimone and theoretical simulation developed in RELAP5 Mod.3.3 environment at the Department of Nuclear Engineering of the University of Palermo (DIN). This paper presents the achieved experimental results for both steady state and transient tests. Moreover, the level of the implementation of the predictive hydraulic model, based on RELAP5 code, as well as its results are described, discussed and compared with the experimental ones.

KW - DIVERTORE

KW - FUSIONE NUCLEARE

KW - ITER

KW - TERMOIDRAULICA

UR - http://hdl.handle.net/10447/48573

M3 - Article

VL - 83

SP - 1034

EP - 1037

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

ER -