International Reactor Dosimetry and Fusion File
IRDFF v.1.02, June 14, 2012

(Cross-section data supersede IRDF-2002)

IAEA Coordinator: Roberto Capote (r.capotenoy@iaea.org)

IRDFF REFERENCES:
R. Capote, K.I. Zolotarev, V.G. Pronyaev, and A. Trkov
Journal of ASTM International (JAI)- Volume 9, Issue 4, April 2012, JAI104119
E.M.Zsolnay, R. Capote, H.K. Nolthenius, and A. Trkov
Technical report INDC(NDS)-0616, IAEA, Vienna, 2012.

The International Reactor Dosimetry and Fusion File (IRDFF) is a standardized evaluated cross section library of neutron dosimetry reactions with uncertainty information that supersedes a widely used IRDF-2002 library. The IRDFF contains cross section data and related decay data for 74 dosimetry reactions, and absorption data for three cover materials B, Cd and Gd used during the irradiation of some specific detectors.

Changes in 1.02:

• Tm169(n,2n) in the whole energy range
• Li-6(n,t); F-19(n,2n); Ni-60(n,p); Cu-63(n,a); Cu-63(n,2n); Cu-65(n,2n); and Zn-64(n,p) above 20 MeV

IRDFF data files (current version version 1.02, June 14, 2012)

• IRDFF rel 1.02 dosimetry cross sections in pointwise ENDF-6 format (compressed)
• IRDFF rel 1.02 dosimetry cross sections in 640 groups ENDF-6 format (compressed)


• Plots of IRDFF v1.02 vs IRDF2002 640g cross sections

Plots of IRDFF reaction rates in reference neutron spectra (IRDFF v1.0)

• Plots of IRDFF reaction rates for a thermal neutron spectrum
• Plots of IRDFF reaction rates for a 1/E neutron spectrum
• Plots of IRDFF reaction rates for a 30 keV Maxwellian neutron spectrum
• Plots of IRDFF reaction rates for Cf252(sf) neutron spectrum

IRDFF neutron spectra

The IRDFF library includes the following neutron spectra:

• MAT = 9228: Prompt fission neutron spectrum for U-235(n_th,f) (ENDF-B/VII.1)
• MAT = 9861: Prompt fission neutron spectrum for Cf-252(sf) (Reich,Mannhart,Englad)
• MAT = 9862: Prompt fission neutron spectrum for U-235(n_th,f) (ENDF-B/VII.0 log int)
• MAT = 9865: Prompt fission neutron spectrum for U-235(n_th,f) (JENDL-4 log int)
• MAT = 9901: Maxwellian at T=0.0253 eV (1.E-5 - 0.55 eV)
• MAT = 9902: Epithermal pure 1/E spectrum (0.55 eV - 2 MeV)
• MAT = 9903: Maxwellian at T=30 keV (MACS in astrophysics)

The library could be used in a broad range of applications from lifetime management assessments of nuclear power reactors and other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. Library evaluations are based mainly on comprehensive experimental data, therefore the reaction library also represents an ideal benchmark collection for validation and improvement of theoretical nuclear reaction modelling.

Validation

Preliminary validation of data is described in the IAEA Technical Report INDC(NDS)-0616
A new Co-ordinated Research Project on "Testing and Improving the IAEA International Dosimetry Library for Fission and Fusion (IRDFF)" has been initiated to validate and test the IRDFF library. Additional information on this new CRP is available here.