|Type||S - Special purpose quantity|
|Sub type||DOS - Dosimetry|
|Quantity||SIG/SPA - Cross section averaged over an incident particle energy spectrum|
|Subfield||Fast fission, D-T fusion|
|Status||Work in progress|
|Latest review date||28-Apr-2022|
Dr Stanislav SIMAKOV at KIT, GER
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.
Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.
Work in progress (as of SG-C review of May 2018)
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