Naismith, O F; Thomas, D J (1996) MCNP calculation of neutron scatter in the main bay of the Chadwick building, NPL. NPL Report. CIRA(EXT)004

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Abstract

The Monte Carlo neutron transport code MCNP has been used to calculate the room and air scattered neutron component at 75 cm from a radionuclide source located at the centre of the low-scatter area in the Chadwick Building, Bldg. 47, at NPL. This is the standard distance used for calibrating personal dosemeters, and the calculation provides information for correcting the response of dosemeters to the scattered radiation. Calculations were performed for both an Am-Be and a 252Cf source. The results were checked by measurements with a Bonner sphere spectrometer set. These measurements revealed that the model used for features within the low-scatter area needs to be refined for calculating scatter at distances further from thle source than 75 cm.

Item Type:	Report/Guide (NPL Report)
NPL Report No.:	CIRA(EXT)004
Subjects:	Ionising Radiation Ionising Radiation > Neutron Metrology
Last Modified:	02 Feb 2018 13:19
URI:	https://eprintspublications.npl.co.uk/id/eprint/417