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The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part I: PWRs

Accepted version
Peer-reviewed

Type

Article

Change log

Authors

Morrison, SL 
Parks, GT 

Abstract

UK plutonium is expected to be managed using uranium-plutonium (U-Pu) mixed oxide (MOX) fuels in Light Water Reactors (LWRs). However, studies have shown that thorium-plutonium (Th-Pu) may be preferential. Research has mostly focussed on recycle of reactor grade Pu with limited minor actinide (MA) content. This study will determine if large quantities of americium (Am) in UK Pu may be restrictive to recycle schemes by determining the effect this has on reactivity feedback coefficients, fissile loading and incineration potential. Addition of Am is shown to result in predictable trends in reactivity feedback coefficients and spatial separation of Am and Pu is found to offer potential advantages over uniformly loaded fuel in terms of maximising fissile loading and incineration. Separation may also offer benefits in terms of targeting Am destruction, particularly if multiple recycle schemes are pursued, as this would maximise the fissile loading requirements while keeping reactivity feedback coefficients negative.

Description

Keywords

Thorium, Plutonium, Americium, Disposition, Spatial separation, PWR, Reduced moderation, MTC, VC

Journal Title

Annals of Nuclear Energy

Conference Name

Journal ISSN

0306-4549
1873-2100

Volume Title

135

Publisher

Elsevier BV
Sponsorship
EPSRC (1642237)