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Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant
Allen D., Thiruarooran C., Thornton D., Fletcher A., Bird A., Rycroft S., Wright G.


Pages: 8    Published: Jan 2007


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Source: STP1490-EB


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: STP45455S
Committee/Subcommittee: E10.08
DOI: 10.1520/STP45455S
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