Error Propagation in Hot-Spot, Hot-Channel Analysis

Tingey, F.H.

doi:10.13182/nse61-a15596

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A Design Evaluations -Fsar1

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2011

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Cited by 5 publications

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“…The design and initial safety evaluation for heat flux used the "hot spot" -"hot channel" approach. The ATR used a statistical approach based on the error propagation method (F. H. Tingey) (15) for bulk water temperature. The pressure, flow rate, bulk coolant, and wall temperatures were computed using an IBM 7040 program developed for this problem.…”

Section: A Design Evaluations -Fsarmentioning

confidence: 99%

Safety Analyses at the Idaho National Engineering and Environmental Laboratory Test Reactor Area: Past to Present

Ambrosek¹,

Ingram²

1999

Heat Transfer: Volume 4

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Test reactors are unique in that the core configuration may change with each operating interval. The process of safety analyses for test reactors at the Idaho National Engineering and Environmental Test Reactor Area has evolved as the computing capabilities, software, and regulatory requirements have changed. The evaluations for experiments and the reactor have moved from measurements in a set configuration and then application to other configurations with a relatively large error to modeling in three-dimensions and explicit analyses for each experiment and operating interval. This evolution is briefly discussed for the Test Reactor Area.

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Section: A Design Evaluations -Fsarmentioning

confidence: 99%