Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase

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Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase. / Jacquet, Patrice; Arbeiter, Frederik; Abou-Sena, Ali; Averhals, Joris; Böttcher, Tim; Chen, Yuming; Dolensky, Bernhard; Fischer, Ulrich; Heinzel, Annette ; Heinzel, Volker; Heupel, Tobias; Klein, Christine; Klix, Axel; Kondo, Keitaro; Konrad, Joachim; Lindau, Rainer; Möslang, Anton; Muche, A.; Piecha, Harald; Rolli, Rolf; Schlindwein, Georg; Schubert, Paul; Schwab, Florian ; Zinn, Kevin.

In: Nuclear Materials and Energy, Vol. 9, 01.12.2016, p. 59-65.

Research output: Contribution to journalArticle

Harvard

Jacquet, P, Arbeiter, F, Abou-Sena, A, Averhals, J, Böttcher, T, Chen, Y, Dolensky, B, Fischer, U, Heinzel, A, Heinzel, V, Heupel, T, Klein, C, Klix, A, Kondo, K, Konrad, J, Lindau, R, Möslang, A, Muche, A, Piecha, H, Rolli, R, Schlindwein, G, Schubert, P, Schwab, F & Zinn, K 2016, 'Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase', Nuclear Materials and Energy, vol. 9, pp. 59-65. https://doi.org/10.1016/j.nme.2016.04.013

APA

Jacquet, P., Arbeiter, F., Abou-Sena, A., Averhals, J., Böttcher, T., Chen, Y., ... Zinn, K. (2016). Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase. Nuclear Materials and Energy, 9, 59-65. https://doi.org/10.1016/j.nme.2016.04.013

Vancouver

Author

Jacquet, Patrice ; Arbeiter, Frederik ; Abou-Sena, Ali ; Averhals, Joris ; Böttcher, Tim ; Chen, Yuming ; Dolensky, Bernhard ; Fischer, Ulrich ; Heinzel, Annette ; Heinzel, Volker ; Heupel, Tobias ; Klein, Christine ; Klix, Axel ; Kondo, Keitaro ; Konrad, Joachim ; Lindau, Rainer ; Möslang, Anton ; Muche, A. ; Piecha, Harald ; Rolli, Rolf ; Schlindwein, Georg ; Schubert, Paul ; Schwab, Florian ; Zinn, Kevin. / Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase. In: Nuclear Materials and Energy. 2016 ; Vol. 9. pp. 59-65.

Bibtex - Download

@article{a23653667edc4c9f9b1b165a173b49f5,
title = "Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase",
abstract = "During the Engineering Validation and Engineering Design Activities (EVEDA) phase (2007-2014) of the International Fusion Materials Irradiation Facility (IFMIF), an advanced engineering design of the High Flux Test Module (HFTM) has been developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the IFMIF neutron source. The development process addressed included manufacturing techniques, CAD, neutronic, thermal-hydraulic and mechanical analyses complemented by a series of validation activities. Validation included manufacturing of 1:1 parts and mockups, test of prototypes in the FLEX and HELOKA-LP helium loops of KIT for verification of the thermal and mechanical properties, and irradiation of specimen filled capsule prototypes in the BR2 test reactor. The prototyping activities were backed by several R&D studies addressing focused issues like handling of liquid NaK (as filling medium) and insertion of Small Specimen Test Technique (SSTT) specimens into the irradiation capsules. This paper provides an up-todate design description of the HFTM irradiation device, and reports on the achieved performance criteria related to the requirements. Results of the validation activities are accounted for and the most important issues for further development are identified.",
keywords = "IFMIF, EVEDA, HFTM, high flux test module, Neutron Irradiation, Irradiation Experiment, SSTT, Fusion, Helium Cooling, Engineering, Design Description, Validation, Prototype",
author = "Patrice Jacquet and Frederik Arbeiter and Ali Abou-Sena and Joris Averhals and Tim B{\"o}ttcher and Yuming Chen and Bernhard Dolensky and Ulrich Fischer and Annette Heinzel and Volker Heinzel and Tobias Heupel and Christine Klein and Axel Klix and Keitaro Kondo and Joachim Konrad and Rainer Lindau and Anton M{\"o}slang and A. Muche and Harald Piecha and Rolf Rolli and Georg Schlindwein and Paul Schubert and Florian Schwab and Kevin Zinn",
note = "Score=10",
year = "2016",
month = "12",
day = "1",
doi = "10.1016/j.nme.2016.04.013",
language = "English",
volume = "9",
pages = "59--65",
journal = "Nuclear Materials and Energy",
issn = "2352-1791",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase

AU - Jacquet, Patrice

AU - Arbeiter, Frederik

AU - Abou-Sena, Ali

AU - Averhals, Joris

AU - Böttcher, Tim

AU - Chen, Yuming

AU - Dolensky, Bernhard

AU - Fischer, Ulrich

AU - Heinzel, Annette

AU - Heinzel, Volker

AU - Heupel, Tobias

AU - Klein, Christine

AU - Klix, Axel

AU - Kondo, Keitaro

AU - Konrad, Joachim

AU - Lindau, Rainer

AU - Möslang, Anton

AU - Muche, A.

AU - Piecha, Harald

AU - Rolli, Rolf

AU - Schlindwein, Georg

AU - Schubert, Paul

AU - Schwab, Florian

AU - Zinn, Kevin

N1 - Score=10

PY - 2016/12/1

Y1 - 2016/12/1

N2 - During the Engineering Validation and Engineering Design Activities (EVEDA) phase (2007-2014) of the International Fusion Materials Irradiation Facility (IFMIF), an advanced engineering design of the High Flux Test Module (HFTM) has been developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the IFMIF neutron source. The development process addressed included manufacturing techniques, CAD, neutronic, thermal-hydraulic and mechanical analyses complemented by a series of validation activities. Validation included manufacturing of 1:1 parts and mockups, test of prototypes in the FLEX and HELOKA-LP helium loops of KIT for verification of the thermal and mechanical properties, and irradiation of specimen filled capsule prototypes in the BR2 test reactor. The prototyping activities were backed by several R&D studies addressing focused issues like handling of liquid NaK (as filling medium) and insertion of Small Specimen Test Technique (SSTT) specimens into the irradiation capsules. This paper provides an up-todate design description of the HFTM irradiation device, and reports on the achieved performance criteria related to the requirements. Results of the validation activities are accounted for and the most important issues for further development are identified.

AB - During the Engineering Validation and Engineering Design Activities (EVEDA) phase (2007-2014) of the International Fusion Materials Irradiation Facility (IFMIF), an advanced engineering design of the High Flux Test Module (HFTM) has been developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the IFMIF neutron source. The development process addressed included manufacturing techniques, CAD, neutronic, thermal-hydraulic and mechanical analyses complemented by a series of validation activities. Validation included manufacturing of 1:1 parts and mockups, test of prototypes in the FLEX and HELOKA-LP helium loops of KIT for verification of the thermal and mechanical properties, and irradiation of specimen filled capsule prototypes in the BR2 test reactor. The prototyping activities were backed by several R&D studies addressing focused issues like handling of liquid NaK (as filling medium) and insertion of Small Specimen Test Technique (SSTT) specimens into the irradiation capsules. This paper provides an up-todate design description of the HFTM irradiation device, and reports on the achieved performance criteria related to the requirements. Results of the validation activities are accounted for and the most important issues for further development are identified.

KW - IFMIF

KW - EVEDA

KW - HFTM

KW - high flux test module

KW - Neutron Irradiation

KW - Irradiation Experiment

KW - SSTT

KW - Fusion

KW - Helium Cooling

KW - Engineering

KW - Design Description

KW - Validation

KW - Prototype

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/35745756

U2 - 10.1016/j.nme.2016.04.013

DO - 10.1016/j.nme.2016.04.013

M3 - Article

VL - 9

SP - 59

EP - 65

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

SN - 2352-1791

ER -

ID: 5647864