Abstract
A methodology is described to evaluate the dosimetry and metallurgical data from the two-year ORR-PSF metallurgical irradiation experiment. The first step is to obtain a three-dimensional map of damage exposure parameter values based on neutron transport calculations and dosimetry measurements which are obtained by means of the LSL-M2 adjustment procedure. Metallurgical test data are then combined with damage parameter, temperature, and chemistry information to determine the correlation between radiation and steel embrittlement in reactor pressure vessels including estimates for the uncertainties. Statistical procedures for the evaluation of Charpy data, developed earlier, are used for this investigation. The data obtained in this investigation provide a benchmark against which the predictions of the ″PSF Blind Test″ can be compared. The results of this investigation and the Blind Test comparison will be discussed.
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References
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© 1985 ECSC, EEC, EAEC, Brussels and Luxembourg
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Stallmann, F.W. (1985). ORNL Evaluation of the ORR-PSF Metallurgical Experiment and “Blind Test. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-5378-9_16
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DOI: https://doi.org/10.1007/978-94-009-5378-9_16
Publisher Name: Springer, Dordrecht
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