A comparison of oxide decay heat simulations and nuclear data libraries with fusion irradiation experiments

A comparison of oxide decay heat simulations and nuclear data libraries with fusion irradiation experiments

A comparison of oxide decay heat simulations and nuclear data libraries with fusion irradiation experiments 150 150 UKAEA Opendata
UKAEA-CCFE-CP(23)55

A comparison of oxide decay heat simulations and nuclear data libraries with fusion irradiation experiments

Cooling water in the primary circuit in both fission and fusion nuclear reactors is unavoidably exposed to neutrons leading to the generation of problematic short-lived isotopes, most importantly, 16N (T1/2=7.3s) via the 16O(n,p)16N reaction. This presents a significant itinerant radiation source to consider for operational dose and impact on radiation sensitive equipment (specifically their electronics), particularly due to the intense 6.13 MeV gamma ray that is emitted during 16N decay. This issue is predicted to be particularly severe in fusion devices such as ITER where the 14 MeV neutron emission rates from the deuterium-tritium plasma will be 1.77 x 1020 n/s and because the energy threshold of the 16O(n,p)16N reaction is above 10 MeV. Due to uncertainties in modelling and nuclear cross section data large safety factors are currently applied within the ITER project and activities are presently ongoing to seek experimental justification to reduce these via coolant loop experiments at the Frascati Neutron Generator. To complement this, we compare existing experimental decay heat data sets measured at the JAEA fusion neutron source (FNS). This experiment employed a fast extraction rabbit system that in certain cases allowed the measurements to capture, at short cooling times, the decay profile of 16N in a range of oxides (K2CO3, CaO, Sc2O3, GeO2, As2O3, StCO3, SnO2, TeO2, IC6H4OH, Cs2O3, La2O3, Sm2O3, Eu2O3, Gd2O3, Tb4O7, Dy2O3, Ho2O3, Er2O3, Tm2O3, Yb2O3, Lu2O3, HgO and Tl2O). Focussing on those data points that can be attributed to 16N, we compare measurements to simulations performed using the FISPACT-II inventory code together with TENDL-2017, EAF-2010, ENDF/B-VIII.0, JEFF-3.3 and JENDL-4.0 evaluated nuclear data libraries. We also derive integral cross section data estimates for 16O(n,p)16N from these oxide measurements and compare with previously obtained measurements in the IAEA EXFOR database and evaluations in the nuclear data libraries themselves. Work supported by RCUK [grant number EP/P012450/1] and the Euratom research and training programme.

Collection:
Conference
Journal:
Publisher:
Conference:
PHYSOR 2020, University of Cambridge, United Kingdom, 29 March - 2 April 2020 - CANCELLED
Published date:
22/02/2021