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Lu Z, Piro M. Computational fluid dynamic investigations of flow bypass through an aged CANDU pressure tube. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109345] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Ryu EH, Park JH, Cho YJ, Lee DH, Jung JY. Benchmarking of the CUPID code to the ASSERT code in a CANDU channel. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.06.030] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Mesh and turbulence model sensitivity analyses of computational fluid dynamic simulations of a 37M CANDU fuel bundle. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.06.004] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Commissioning of an MRI test facility for CFD-grade flow experiments in replicas of nuclear fuel assemblies and other reactor components. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111080] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Piro M, Christon M, Tensuda B, Poschmann M, Bruschewski M, Grundmann S, Tropea C. Fluid flow in a diametrally expanded CANDU fuel channel – Part 2: Computational study. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110372] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Bruschewski M, Piro M, Tropea C, Grundmann S. Fluid flow in a diametrally expanded CANDU fuel channel – Part 1: Experimental study. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110371] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Piro M, Sunderland D, Revie W, Livingstone S, Dimayuga I, Douchant A, Wright M. POTENTIAL MITIGATION STRATEGIES FOR PREVENTING STRESS CORROSION CRACKING FAILURES IN HIGH-BURNUP CANDU FUEL. CNL NUCLEAR REVIEW 2018. [DOI: 10.12943/cnr.2016.00011] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Potential mitigation strategies for preventing stress corrosion cracking (SCC) failures in CANDU fuel cladding that are based on lessons learned on both domestic and international fronts are discussed in this paper. Although SCC failures have not been a major concern in CANDU reactors in recent decades, they may resurface at higher burnup for conventional fuels or with nonconventional fuels that are currently being investigated, such as MOX or thoria-based fuels. The motivation of this work is to provide the foundation for considering possible remedies for SCC failures. Three candidate remedies are discussed, namely improved fabrication methods for fuel appendages, barrier-liner cladding, and fuel doping. In support of this effort, recent advances in experimental characterization methods are described—methods that have been successfully used in non-nuclear materials that can be used to further elucidate SCC behaviour in CANDU fuel. The overall objective is to outline a path forward for characterizing material behaviour as an essential part of investigating remedies to SCC failure. This will allow increased fuel discharge burnup, maximum linear power, and plant manoeuvrability, while maintaining a high degree of reliability.
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Affiliation(s)
- Markus Piro
- Canadian Nuclear Laboratories, 286 Plant Road, Chalk River, ON K0J 1J0, Canada
| | - Dion Sunderland
- Pacific Northwest National Laboratory, Richland, WA 99352, USA
| | | | - Steve Livingstone
- Canadian Nuclear Laboratories, 286 Plant Road, Chalk River, ON K0J 1J0, Canada
| | - Ike Dimayuga
- Canadian Nuclear Laboratories, 286 Plant Road, Chalk River, ON K0J 1J0, Canada
| | - Alain Douchant
- Canadian Nuclear Laboratories, 286 Plant Road, Chalk River, ON K0J 1J0, Canada
| | - Michael Wright
- Canadian Nuclear Laboratories, 286 Plant Road, Chalk River, ON K0J 1J0, Canada
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Fadaee M, Yu SD. Effects of Endcaps and Spacer Pads on Unsteady Fluid Forces and Flow Through a 37-Element CANDU Fuel Bundle. NUCL SCI ENG 2017. [DOI: 10.1080/00295639.2017.1337382] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
Affiliation(s)
- M. Fadaee
- Ryerson University, Department of Mechanical and Industrial Engineering, Toronto, Ontario M5B 2K3, Canada
| | - S. D. Yu
- Ryerson University, Department of Mechanical and Industrial Engineering, Toronto, Ontario M5B 2K3, Canada
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