ISSN: 1546-962X
CODEN: JAIOAD
Published Online: 1 April 2012
Page Count: 12

A Three-Dimensional Methodology for the Assessment of Neutron Damage and Nuclear Energy Deposition in Graphite Components of Advanced Gas-Cooled Reactors

Morgan, D. O.
TCS, Serco, Gloucester, Gloucestershire

Robinson, A. T.
TCS, Serco, Gloucester, Gloucestershire

Allen, D. A.
TCS, Serco, Gloucester, Gloucestershire

Picton, D. J.
TCS, Serco, Gloucester, Gloucestershire

Thornton, D. A
TCS, Serco, Gloucester, Gloucestershire

Shaw, S. E.
EDF Energy, Gloucester,

(Received 18 May 2011; accepted 14 December 2011)

Abstract

This paper describes the development of a three-dimensional methodology for the assessment of neutron damage and nuclear energy deposition (or nuclear heating) throughout the graphite cores of the UK’s Advanced Gas-cooled Reactors. Advances in the development of the Monte Carlo radiation transport code MCBEND have enabled the efficient production of detailed fully three-dimensional models that utilise three-dimensional source distributions obtained from Core Follow data supplied by the reactor physics code PANTHER. The calculational approach can be simplified to reduce both the requisite number of intensive radiation transport calculations, as well as the quantity of data output. These simplifications have been qualified by comparison with explicit calculations and they have been shown not to introduce significant systematic uncertainties. Simple calculational approaches are described that allow users of the data to address the effects on neutron damage and nuclear energy deposition predictions of the feedback resulting from the mutual dependencies of graphite weight loss and nuclear energy deposition.

Keywords:
Advanced Gas-cooled Reactors, graphite dosimetry, neutron damage, radiolytic oxidation, MCBEND, Monte Carlo

Paper ID: JAI104002
DOI: 10.1520/JAI104002
ASTM International is a member of CrossRef.