Validation of IRDFF-II library by means of 252 Cf spectral averaged cross sections.

Spectrum-averaged cross sections (SACS) is an important quantity usable in validation of nuclear cross sections. Especially in case of dosimetrical reactions there is a request on precise validation. This paper presents SACS measured in the reference ²⁵² Cf(sf) neutron field for neutron dosimetry reactions to validate recently updated IRDFF-II library intended mainly for neutron metrology applications. It covers ⁴⁶ Ti(n,p) ⁴⁶ Sc, ⁴⁷ Ti(n,p) ⁴⁷ Sc, ⁴⁸ Ti(n,p) ⁴⁸ Sc, ⁵⁸ Ni(n,p) ⁵⁸ Co, ⁶⁰ Ni(n,p) ⁶⁰ Co, ⁵⁸ Ni(n,2n) ⁵⁷ Ni, ²⁴ Mg(n,p) ²⁴ Na, ²⁷ Al(n,α) ²⁴ Na and ⁶³ Cu(n,α) ⁶⁰ Co threshold reactions. Measurement of ⁶⁰ Ni(n,p) ⁶⁰ Co SACS is included in NEA's High Priority Nuclear Data Request List since existing data are discrepant. Spectral averaged cross sections were derived from experimentally determined reaction rates by gamma spectrometry using a same high-purity germanium detector to measure all irradiated samples. Measured spectrum-averaged cross sections agree very well within quoted uncertainties with those calculated using the IRDFF-II library. No other library achieves such good performance. Thus, the presented data support use of the cross sections of the mentioned reactions from IRDFF-II library.
(Copyright © 2019 Elsevier Ltd. All rights reserved.)