Title of article :
Neutronics diagnostics for European ITER TBMs: Activation foil spectrometer for short measurement cycles
Author/Authors :
Klix، نويسنده , , A. and Domula، نويسنده , , A. and Fischer، نويسنده , , U. and Gehre، نويسنده , , D. and Pereslavtsev، نويسنده , , P. and Rovni، نويسنده , , I.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2012
Pages :
6
From page :
1301
To page :
1306
Abstract :
An important aim of neutronics Test Blanket Module (TBM) experiments in ITER will be to check the prediction accuracy of nuclear responses in an environment closer to a future fusion power reactor than so far provided by existing facilities. The development of measurement methods suitable for the harsh environment in an ITER TBM has been addressed in several recent R&D programs supported by Euratom. Within this framework, KIT is developing an activation foil spectrometer for the measurement of local neutron flux densities in the TBM. We intend to establish a measurement method which allows to record the induced activities in small packages of activation foils simultaneously and to calculate the corresponding spectral neutron flux densities with moderate time resolution of tens of seconds immediately after extraction from the TBM. In the present work we propose a candidate set of activation foil materials which cover the neutron energy range from thermal to 14 MeV. In order to assess their basic suitability for such measurements, we have computed induced gamma-ray activities in the foils using a calculated neutron spectrum in a representative position in the European HCPB TBM assuming a short irradiation time of 30 s. In a further step we have investigated pulse height spectra which would be obtained in a typical gamma-ray measurement arrangement in a HPGe detector and concluded that the proposed set of activation foils should be basically suitable for such a measurement system but require improvement of relevant cross sections uncertainties.
Keywords :
Activation foil , Neutron flux spectrometer , Neutron flux density , Test blanket module
Journal title :
Fusion Engineering and Design
Serial Year :
2012
Journal title :
Fusion Engineering and Design
Record number :
2360603
Link To Document :
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