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Battelle’s Columbus Laboratories Reactor Vessel Surveillance Service Activities

  • Conference paper
Reactor Dosimetry

Abstract

This paper describes the current methodology in use at Battelle’s Columbus Laboratories for obtaining and processing pressure vessel surveillance data, extrapolating mechanical behavior, and calculating reactor coolant pressure-temperature operating curves. Recent results from the Arkansas Nuclear One—Unit 2 (ANO-2) benchmark cavity dosimetry experiment are reported. The results indicate that it is possible to calculate the flux in ex- vessel locations with accuracies on the order of 10-15 percent. Also, end of life metallurgical predictions for the Poolside Facility (PSF) Blind Test materials are compared with experimental data.

Another Batelle-Columbus research activity related to pressure vessel surveillance in fracture initiation and arrest toughness determination using miniature specimens. Small-sized laboratory specimens provide data which can be extremely non-conservative compared with large inservice structures and which exhibit considerable scatter. Battele-Columbus has examined these effects and has developed a simple method for minimixing them.

The radiation-induced temperature shift to crack arrest toughness has been measured and found to be significanty less for high-cooper materials than estimated from the shift in the Charpy 40.7 Joule temperature or from U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99 (Rev. 1) calculations. A method has been developed for estimating crack arrest toughness as a function of fluence which is still conservative for high-copper materials but significantly less restrictive.

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Author information

Authors and Affiliations

  1. Battelle’s Columbus Laboratories, Columbus, Ohio, 43201, USA

    M. P. Manahan, A. R. Rosenfield, C. W. Marschall & M. P. Landow

Authors
  1. M. P. Manahan
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  2. A. R. Rosenfield
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  3. C. W. Marschall
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  4. M. P. Landow
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Editor information

Editors and Affiliations

  1. Commissariat à l’Energie Atomique, Centre d’Etudes Nucleaires, Cadarache, France

    J. P. Genthon

  2. Commission of the European Communities, Joint Research Centre, Petten Establishment, Petten, The Netherlands

    H. Röttger

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© 1985 ECSC, EEC, EAEC, Brussels and Luxembourg

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Manahan, M.P., Rosenfield, A.R., Marschall, C.W., Landow, M.P. (1985). Battelle’s Columbus Laboratories Reactor Vessel Surveillance Service Activities. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-5378-9_10

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  • DOI: https://doi.org/10.1007/978-94-009-5378-9_10

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-94-010-8873-2

  • Online ISBN: 978-94-009-5378-9

  • eBook Packages: Springer Book Archive

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