|Type||S - Special purpose quantity|
|Sub type||DOS - Dosimetry|
|Quantity||SIG/SPA - Cross section averaged over an incident particle energy spectrum|
|Incident energy||252Cf(sf) - 235U(n,f)|
|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].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
Work in progress (as of SG-C review of May 2018)
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