Development of a Used Fuel Container for Nuclear Fuel Waste
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'HYHORSPHQWRID8VHG)XHO&RQWDLQHUIRU1XFOHDU)XHO:DVWH Peter Maak Ontario Power Generation 700 University Avenue, Toronto, Ontario, Canada. M3B 3J7 $%675$&7 The deep geologic repository (DGR) concept is one of the approaches being considered in Canada for long-term management of used CANDU fuel. The Canadian concept entails encapsulating used CANDU fuel bundles in durable used-fuel containers (UFCs) and burying the UFCs in an engineered repository at depth in the Canadian Shield. Currently, an updated concept for a DGR is being prepared by Ontario Power Generation (OPG). This technical paper describes OPG’s studies from 1999 to 2002 that have led to the development of an updated reference UFC design. The updated UFC design holds 324 used CANDU fuel bundles. It consists of an outer corrosion-resistant oxygen-free phosphorousdoped copper vessel and an inner load-bearing steel vessel. The used-fuel bundles are placed within a fuel basket for handling and loading into the UFC. This reference UFC design would be used for future safety assessment and engineering studies. ,1752'8&7,21 The Canadian concept for a deep geologic repository (DGR) for nuclear fuel waste comprise a system of multiple barriers that include used CANDU reactor fuel, container, buffer, sealing systems and the geosphere. The DGR concept entails encapsulating used fuel in durable usedfuel containers (UFCs) and burying the UFCs in an engineered repository located at a depth of 500 to 1000 m in the stable plutonic rock of the Canadian Shield. Currently, an updated concept for a DGR is being prepared by Ontario Power Generation (OPG). OPG’s studies from 1999 to 2002 that have led to the development of an updated reference UFC design. The basic duel vessel UFC design consists of an outer corrosion-barrier vessel and an inner load-bearing vessel. These studies can be divided into three major areas: a) selection of a material for the outer corrosion-resistant vessel; c) selection of a inner load-bearing component design; and c) selection of a limited number of container fuel capacities and geometries. &217$,1(5'(9(/230(17$/:25. D 6HOHFWLRQRID5HIHUHQFH&RUURVLRQ%DUULHU0DWHULDO An extensive literature review was carried out by OPG on the current state of knowledge of titanium alloys (Ti-2, Ti-12 and Ti-16) and oxygen-free phosphorous-doped copper (OFP-Cu) as potential corrosion-barrier materials for the UFC. The Ti alloys have been studied extensively by Atomic Energy of Canada Limited (AECL) [1]. The OFP-Cu material is the reference corrosion-barrier materials chosen in the Swedish and Finish nuclear waste management programs [2,3]. Based on the consideration of information provided in this review, and analyses of a number of programmatic factors (i.e., knowledge for predicting the long-term performance
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and safety a UFC in a DGR, financial implication, support from other international nuclear waste management programs, natural analogues), the OFP-Cu material was selected as the reference corrosion barrier material for the outer ves
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