|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)|
|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
Measurements of the 252Cf(sf)-spectrum-averaged cross section are missing for validation purposes. New measurements of the 235U(n,f)-spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_Cf252U235.pdf below.
Work in progress (as of SG-C review of May 2018)
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