Re-evaluation of the irradiation conditions in the IFMIF test cell based on the EVEDA phase design

Kondo, Keitaro; Arbeiter, Frederik; Fischer, U.; Große, Daniel; Heinzel, V.; Klix, A.; Serikov, A.; Tian, Kuo; Weber, Virginia

doi:10.1016/j.fusengdes.2013.05.029

Cited by 7 publications

(11 citation statements)

References 8 publications

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“…Similar analyses were carried out in the past for the IFMIF facility [17][18][19]. One may expect similar performances for DEMO, but due to the different configuration of the facility new results are obtained and quantified following different criteria.…”

Section: Introductionsupporting

confidence: 55%

“…As previously mentioned, only the volume with the higher dose rate will be used in IFMIF-DONES to irradiate structural materials: the high flux area of about 0.5 l volume and a neutron fluence of typically 10 17 n m −2 s −1 , inducing up to 20 dpa/ full power year (iron equivalent) in the materials. In figure 2 the current CAD design of the HFTM [19,21,22] assembly and the irradiation rigs with specimen is shown. In the beam footprint region, the HFTM is built from a thin walled container divided into eight compartments; three rigs can be placed on each of them (a total of 24 rigs, 720 cm 3 volume available for specimens).…”

Section: Mcnp Geometrical Modelmentioning

confidence: 99%

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Sensitivity of IFMIF-DONES irradiation characteristics to different design parameters

Mota¹,

Ibarra²,

García³

et al. 2015

Nucl. Fusion

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The DONES (DEMO oriented neutron source) has been conceived as a simplified IFMIF-like plant to provide earlier availability, on a reduced time scale and with a reduced budget-both compared to IFMIF-of basic information on materials damage. The conceptual design of the DONES will consist of a number of changes oriented to reduce the time required for construction and the time required to produce the required damage.This paper evaluates how changes in beam irradiation parameters or geometric issues will affect the damage produced in the specimens located in the experimental irradiation area (test cell) of the DONES. Neutron transport calculations have been performed to evaluate the sensitivity of material radiation effects to different irradiation environments. The neutron transport calculations have been performed using McDeLicious 2011 (based on MCNP5-v1.6), code developed by the KIT research institute to reproduce the IFMIF deuteron-lithium neutron source.With this aim in mind, the materials radiation effects evaluated to analyse the sensitivity to the changes in the irradiation conditions have been the damage dose rate, the He and H production, and the He and H production to damage dose ratio. With the analysis of these parameters it is possible to make an evaluation of the level of primary damage suffered by the specimen placed in the high flux test module (HFTM).Based on results obtained in this paper and taking into account engineering considerations, substantial progress should be possible regarding the optimum design parameters for the irradiation area of the IFMIF-DONES facility.

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Section: Introductionsupporting

confidence: 55%

Section: Mcnp Geometrical Modelmentioning

confidence: 99%

Sensitivity of IFMIF-DONES irradiation characteristics to different design parameters

Mota¹,

Ibarra²,

García³

et al. 2015

Nucl. Fusion

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“…As it has been previously mentioned, only the volume with the higher dose rate will be used in IFMIF-DONES to irradiate structural materials: a high flux area of about 0.5 litre and a neutron fluence rate of typically 10 17 n m −2 s −1 , inducing up to 20 dpa fpy −1 (iron equivalent) in the materials are foreseen. In figure 2 the current CAD design of the HFTM [24,32,33] assembly and the irradiation rigs with specimen is shown. In the beam footprint region, the HFTM is built from a thin walled container divided into 8 compartments, and 3 rigs can be placed on each of them (a total of 24 rigs, 720 cm 3 volume available for specimens).…”

Section: Ifmif-dones (Demo Oriented Neutron Source)mentioning

confidence: 99%

“…The volume fraction considered for experimental specimen packaging is the same for all the materials evaluated. The packaging used is 74.19% of the material under study and 25.81% of NaK, as specified in the HFTM DDD report [33].The criterium chosen to evaluate whether the kind of samples distribution in the HFTM is optimal or not, was selected assessing how close are the damage dose rate or the gas production to damage dose ratio from the values expected in the nuclear fusion reactor. They can be divided in three studies, cases in which a dedicated irradiation campaign is designed, cases in which a joint irradiation campaign is tested and the cases in which a optimization of the irradiation area have been tried.…”

Section: Evaluation Of Cases With Different Alloy Loadingmentioning

confidence: 99%

Potential irradiation of Cu alloys and tungsten samples in DONES

Mota¹,

Palermo²,

Laces³

et al. 2017

Nucl. Fusion

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“…Because IFMIF utilizes the d-Li nuclear reaction with deuterons energy of 40 MeV, high energy neutrons up to 55 MeV are produced [8]. As for the shielding benchmark in the energy range above 20 MeV, the TIARA transmission experiments through iron and concrete using p-Li quasi-monoenergetic neutron source [9,10] have been analyzed using FENDL-3/SLIB4.…”

Section: Introduction Amentioning

confidence: 99%

Analyses of shielding benchmark experiments using FENDL-3 cross-section data starter library for ITER and IFMIF applications

Kondo

Fischer

Pereslavtsev

et al. 2014

Progress in Nuclear Science and Technology

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Recently IAEA has been conducting a coordinated research project to update the FENDL-2.1 nuclear data library to FENDL-3. In the present study, FENDL-3, Starter Library, Release 4 (FENDL-3/SLIB4) has been extensively tested through analysis of many fusion relevant benchmark problems. FENDL-3/SLIB4 gives better results for the FNG ITER shielding benchmark and the tungsten benchmark experiments than the previous FENDL-2.1. As for the shielding benchmark in the neutron energy range above 20 MeV, the TIARA transmission experiments through iron and concrete using p-Li quasi-monoenergetic neutron source have been analyzed. FENDL-3/SLIB4 provides satisfactory results for the TIARA shielding benchmark through iron. For concrete, however, some discrepancy was found. The present analysis suggests importance of 16 O data in the neutron energy range above 20 MeV for shielding calculations through concrete.

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Re-evaluation of the irradiation conditions in the IFMIF test cell based on the EVEDA phase design

Cited by 7 publications

References 8 publications

Sensitivity of IFMIF-DONES irradiation characteristics to different design parameters

Sensitivity of IFMIF-DONES irradiation characteristics to different design parameters

Potential irradiation of Cu alloys and tungsten samples in DONES

Analyses of shielding benchmark experiments using FENDL-3 cross-section data starter library for ITER and IFMIF applications

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