SAFETY ANALYSIS REPORT, ADVANCED TEST REACTOR. Volume 1

deBoisblanc, D.R.; Cohen, S

doi:10.2172/4495135

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Neutronic Analysis a Design Evaluations1

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1999

2023

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Cited by 3 publications

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“…Measurements in the ATRC showed that voiding a flux trap and experiment resulted in the maximum accident consequences for a reactivity insertion. The evaluations showed a peak reactor power greater than 10 times normal with an integrated energy of 130 MWsec (1) . The results are shown in Figure 1.…”

Section: Neutronic Analysis a Design Evaluationsmentioning

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: Neutronic Analysis a Design Evaluationsmentioning

confidence: 99%