Regulatory approaches in mitigating chemical degradation of zirconium alloys in the design and operation of light water reactors

2021 ◽  
Author(s):  
P. Wiringgalih ◽  
Y. Pramono
Keyword(s):  
Zirconium Alloys ◽  
Chemical Degradation ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors

scholarly journals IRRADIATION EFFECTS ON ZR-2.5NB IN POWER REACTORS

2016 ◽  
Vol 5 (1) ◽  
pp. 17-36 ◽  
Author(s):  
Carol Song
Keyword(s):  
Mechanical Properties ◽  
Operating Experience ◽  
Zirconium Alloys ◽  
Light Water Reactors ◽  
Irradiation Effects ◽  
Light Water ◽  
Current State ◽  
Structural Applications ◽  
Water Reactors ◽  
Reactor Operating

Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, “High Power Channel-type Reactor”) reactors for over 40 years. In a recent report from the Electric Power Research Institute, Zr-2.5Nb was identified as one of the candidate materials for use in normal structural applications in light-water reactors owing to its increased resistance to irradiation-induced degradation as compared with currently used materials. Historically, the largest program of in-reactor tests on zirconium alloys was performed by Atomic Energy of Canada Limited. Over many years of in-reactor testing and CANDU operating experience with Zr-2.5Nb, extensive research has been conducted on the irradiation effects on its microstructures, mechanical properties, deformation behaviours, fracture toughness, delayed hydride cracking, and corrosion. Most of the results on Zr-2.5Nb obtained from CANDU experience could be used to predict the material performance under light water reactors. This paper reviews the irradiation effects on Zr-2.5Nb in power reactors (including heavy-water and light-water reactors) and summarizes the current state of knowledge.

Performance of Zirconium Alloys in Light Water Reactors with a Review of Nodular Corrosion

2010 ◽  
Vol 7 (6) ◽  
pp. 103032 ◽  
Author(s):  
David G. Franklin ◽  
P. Barberis ◽  
S. W. Dean
Keyword(s):  
Zirconium Alloys ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
New Approach ◽  
Light Water ◽  
Water Reactors
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