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The mechanical integrity of fuel pin cladding in a pulsed-beam accelerator driven subcritical reactor

Ahmad, A and Parks, GT (2012) The mechanical integrity of fuel pin cladding in a pulsed-beam accelerator driven subcritical reactor. Annals of Nuclear Energy, 42. pp. 35-42. ISSN 0306-4549

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The Accelerator Driven Subcritical Reactor (ADSR) is one of the reactor designs proposed for future nuclear energy production. Interest in the ADSR arises from its enhanced and intrinsic safety characteristics, as well as its potential ability to utilize the large global reserves of thorium and to burn legacy actinide waste from other reactors and decommissioned nuclear weapons. The ADSR concept is based on the coupling of a particle accelerator and a subcritical core by means of a neutron spallation target interface. One of the candidate accelerator technologies receiving increasing attention, the Fixed Field Alternating Gradient (FFAG) accelerator, generates a pulsed proton beam. This paper investigates the impact of pulsed proton beam operation on the mechanical integrity of the fuel pin cladding. A pulsed beam induces repetitive temperature changes in the reactor core which lead to cyclic thermal stresses in the cladding. To perform the thermal analysis aspects of this study a code that couples the neutron kinetics of a subcritical core to a cylindrical geometry heat transfer model was developed. This code, named PTS-ADS, enables temperature variations in the cladding to be calculated. These results are then used to perform thermal fatigue analysis and to predict the stress-life behaviour of the cladding. © 2011 Elsevier Ltd. All rights reserved.

Item Type: Article
Divisions: Div A > Energy
Depositing User: Unnamed user with email
Date Deposited: 18 May 2016 18:47
Last Modified: 30 Jul 2016 22:22
DOI: 10.1016/j.anucene.2011.12.012