Abstract This paper shows the calculations of radioactivity and afterheat
in the components of the China Spallation Neutron Source (CSNS) target
station, with the Monte Carlo codes LAHET, MCNP4C and the multigroup
code CINDER'90. These calculations provide essential data for the
detailed design and maintenance of the CSNS target station.
Received: 06 November 2008
Revised: 05 January 2009
Published: 20 September 2009