AECL Technologies (AECLT), the 100%-owned US subsidiary of Atomic Energy of Canada Ltd. (AECL), is currently the proponents of a pre-licensing review of the Advanced CANDU® Reactor (ACR™)* with the United States Nuclear Regulatory Commission (USNRC). A key focus topic for this pre-application review is the NRC acceptance of the computer codes used in the safety analysis of the ACR. These codes have been developed and their predictions compared against experimental results over extended periods of time in Canada. These codes have also undergone formal validation in the 1990’s. In support of this formal validation effort AECL has developed, implemented and currently maintains a Software Quality Assurance program (SQA) to ensure that its analytical, scientific and design computer codes meet the required standards for software used in safety analyses. This paper discusses the SQA program used to develop, qualify and maintain the computer codes used in ACR safety analysis, including the current program underway to confirm the applicability of these computer codes for use in ACR safety analyses.
- Nuclear Engineering Division
Computer Code Applicability Assessment for the Advanced CANDU Reactor
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Wren, DJ, Popov, N, Langman, VJ, & Snell, VG. "Computer Code Applicability Assessment for the Advanced CANDU Reactor." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 397-404. ASME. https://doi.org/10.1115/ICONE12-49101
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