Validation of absolute axial neutron flux distribution calculations with MCNP with 197Au(n,γ)198Au reaction rate distribution measurements at the JSI TRIGA Mark II reactor

Appl Radiat Isot. 2014 Feb:84:57-65. doi: 10.1016/j.apradiso.2013.11.027. Epub 2013 Nov 20.

Abstract

The calculation of axial neutron flux distributions with the MCNP code at the JSI TRIGA Mark II reactor has been validated with experimental measurements of the (197)Au(n,γ)(198)Au reaction rate. The calculated absolute reaction rate values, scaled according to the reactor power and corrected for the flux redistribution effect, are in good agreement with the experimental results. The effect of different cross-section libraries on the calculations has been investigated and shown to be minor.

Keywords: Axial neutron flux distributions; MCNP; Monte Carlo calculations; Neutron activation measurements; TRIGA reactor.