Validation of IRDFF in²⁵²Cf Standard and IRDF-2002 Reference Neutron Fields

Abstract

Abstract.The results of validation of the latest release of International Reactor Dosimetry and Fusion File, IRDFF-1.03, in the standard 252 Cf(s.f.) and reference 235 U(n th ,f) neutron benchmark fields are presented. The spectrum-averaged cross sections were shown to confirm IRDFF-1.03 in the 252 Cf standard spontaneous fission spectrum; that was not the case for the current recommended spectra for 235 U(n th ,f). IRDFF was also validated in the spectra of the research reactor facilities ISNF, Sigma-Sigma and YAYOI, which are available in the IRDF-2002 collection. The ISNF facility was re-simulated to remove unphysical oscillations in the spectrum. IRDFF-1.03 was shown to reproduce reasonably well the spectrum-averaged data measured in these fields except for the case of YAYOI.

Use of Neutron Benchmark Fields for the Validation of Dosimetry Cross Sections

“…The author first, erroneously, thought that this difference in validation results may be related to the use of a coarse group structure representation of the 235 U(th) spectrum in the original NBS reported analysis and to the presence of a low energy room-scatter neutron contribution to the measurement. However, work recently reported by Simakov [10] clearly indicates that the discrepancy seen in Fig. 3b is due to a failure to include other helium production reactions in this analysis.…”

EXFOR – a global experimental nuclear reaction data repository: Status and new developments

“…The dosimetry reaction cross-sections are employed for the determination and monitoring of neutron fluence and spectra at different facilities as well as for assessments of operational safety. An on-going IAEA coordinated research project (CRP) on "Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF)" is providing an updated library in the energy range up to 60 MeV [6]. The EXFOR database has been assessed for: …”