Validation of activation calculations using the Intermediate Energy Activation File IEAF-2001

Fischer, U.; Simakov, S.P.; Möllendorff, Ulrich von; Pereslavtsev, P.; Wilson, Paul P. H.

doi:10.1016/s0920-3796(03)00113-3

Cited by 8 publications

(9 citation statements)

References 3 publications

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“…Our results are in general in good agreement with those obtained by ALARA and FISPACT codes [2,3]. However, discrepancies up to 30% have been found for a few isotopes ( 52 Fe, 87m Y).…”

Section: Computational Methodology and Validation Processsupporting

confidence: 91%

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Transmutation analysis of realistic low-activation steels for magnetic fusion reactors and IFMIF

Cabellos

Sanz

García-Herranz

et al. 2007

Journal of Nuclear Materials

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“…Our results are in general in good agreement with those obtained by ALARA and FISPACT codes [2,3]. However, discrepancies up to 30% have been found for a few isotopes ( 52 Fe, 87m Y).…”

Section: Computational Methodology and Validation Processsupporting

confidence: 91%

“…In earlier work, different inventory computational codes, previously developed for fusion applications, have shown to be reliable for IFMIF applications with appropriated modifications [2,3]. Following the same trend, this capability has been incorporated into the ACAB code [4].…”

Section: Introductionmentioning

confidence: 99%

Transmutation analysis of realistic low-activation steels for magnetic fusion reactors and IFMIF

Cabellos

Sanz

García-Herranz

et al. 2007

Journal of Nuclear Materials

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“…This has led to various versions of the European Activation A dedicated Intermediate Energy Activation File, IEAF-2001, was previously developed for neutron-induced activation cross sections up to 150 MeV [21]. An update of this data file is currently underway [22].…”

Section: Activation Cross Section Datamentioning

confidence: 99%

Development needs of nuclear data for fusion technology

Fischer

Batistoni

Forrest

et al. 2007

Nd2007

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“…1, of different degrees of hardness are proposed to study the behaviour of fissile materials: (i) the fast component of a high neutrón flux with a significant thermal contribution common in a material testing reactor such as BR2 [3], (ii) the fusión power in a DEMO magnetic fusión reactor [4], and (iii) the fast neutrón in the IFMIF high flux test module [4].…”

Section: Introductionmentioning

confidence: 99%

Assessment of fissionable material behaviour in fission chambers

Cabellos

Fernandez

Rapisarda³

et al. 2010

Nuclear Instruments and Methods in Physics Research Section A:

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Keywords:Fission chamber BR2 DEMO IFMIF Uncertainty cross-sections A comprehensive study is performed in order to assess the pertinence of fission chambers coated with different fissile materials for high neutrón flux detection. Three neutrón scenarios are proposed to study the fast component of a high neutrón flux: (i) high neutrón flux with a significant thermal contribution such as BR2, (ii) DEMO magnetic fusión reactor, and (iii) IFMIF high flux test module.In this study, the inventory code ACAB is used to analyze the following questions: (i) impact of different deposits in fission chambers; (ii) effect of the irradiation time/burn-up on the concentration; (iii) impact of activation cross-section uncertainties on the composition of the deposit for all the range of burn-up/irradiation neutrón fluences of interest. The complete set of nuclear data (decay, fission yield, activation cross-sections, and uncertainties) provided in the EAF2007 data library are used for this evaluation.

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Validation of activation calculations using the Intermediate Energy Activation File IEAF-2001

Cited by 8 publications

References 3 publications

Transmutation analysis of realistic low-activation steels for magnetic fusion reactors and IFMIF

Transmutation analysis of realistic low-activation steels for magnetic fusion reactors and IFMIF

Development needs of nuclear data for fusion technology

Assessment of fissionable material behaviour in fission chambers

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