ISSN: 1546-962X
CODEN: JAIOAD
Published Online: 5 April 2006
Page Count: 8

Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant

Allen, DA
British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

Thiruarooran, C
British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

Thornton, DA
British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

Fletcher, AL
British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

Bird, AJ
Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

Rycroft, S
Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

Wright, GA
Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

(Received 20 June 2005; accepted 5 February 2006)

Abstract

This paper describes the methodology and results of Monte Carlo neutron transport calculations performed to determine the neutron fluxes required for assessments of radioactive inventories of Magnox power plant. Use has been made of existing validated Monte Carlo models of the plant, which have been extended to include details beyond the pressure vessels to the outer surface of the biological shield.

Keywords:
decommissioning, radioactive inventory, magnox power plant, monte carlo, MCBEND

Paper ID: JAI100364
DOI: 10.1520/JAI100364
ASTM International is a member of CrossRef.