Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Investigation on failure assessment method for nuclear graphite components

  • Gao, Yantao (Division of Nuclear Materials Science and Engineering, Shanghai Institute of Applied Physics, Chinese Academy of Sciences) ;
  • Tsang, Derek K.L. (Division of Nuclear Materials Science and Engineering, Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
  • Received : 2019.04.17
  • Accepted : 2019.07.04
  • Published : 2020.01.25
Download PDF
⟨ Previous Next ⟩

Abstract

Super fine-grained graphite is a type of advanced nuclear graphite which was developed for Molten Salt Reactor (MSR). It is necessary to establish a failure assessment method used for nuclear graphite components in MSR. A modified assessment approach based on ASME BPVC-III-5_2017 is presented. The new approach takes a new parameter, KIC, into account and abandons the parameter, grain size, which is unrealistic for super fine-grained graphite as the computation is enormous if we use conventional methods. Three methodologies (KTA 3232, ASME, New approach) were also evaluated by theoretical prediction and experimental verification. The results indicated the new developed code can be used for design and failure assessment of super fine-graphite components and has more extensive applicability.

Keywords

References

  1. J. Serp, M. Allibert, O. Benes, et al., The molten salt reactor (MSR) in generation IV: overview and perspectives, Prog. Nucl. Energy 77 (2014) 308-319. https://doi.org/10.1016/j.pnucene.2014.02.014
  2. T.H. Becker, T.J. Marrow, R.B. Tait, Damage, crack growth and fracture characteristics of nuclear grade graphite using the Double Torsion technique, J. Nucl. Mater. 414 (2011) 32-43. https://doi.org/10.1016/j.jnucmat.2011.04.058
  3. T. Becker, Understanding and Modelling Damage and Fracture in Nuclear Grade Graphite, University of Cape Town, 2011.
  4. KTA-3232, Ceramic Components of Reactor Pressure Vessel (Draft), 1992.
  5. R.J. Price, Statistical study of the strength of near-Isotropic graphite, Gen. Atom. Proj. 3224 (1976).
  6. F. Ho, Modified Weibull Theory for the Strength of Granular Brittle Material, General Atomic company, 1979.
  7. J.E. Brocklehurst, M.I. Darby, Concerning the fracture of graphite under different test conditions, Mater. Sci. Eng. 16 (1974) 91-106. https://doi.org/10.1016/0025-5416(74)90143-8
  8. J.P. Strizak, The Effect of Volume on the Tensile Strength of Several Nuclear Grade Graphites, Specific Nuclear Reactors & Associated Plants, 1991.
  9. M.P. Hindley, M.N. Mitchell, C. Erasmus, et al., A numerical stress based approach for predicting failure in NBG-18 nuclear graphite components with verification problems, J. Nucl. Mater. 436 (2013) 175-184. https://doi.org/10.1016/j.jnucmat.2012.10.030
  10. ASME Boiler and Pressure Vessel Code, SECTION III Rules for Construction of Nuclear Facility Components, HHA-3217 Calculation of Probability of Failure, 2017.
  11. T. Burchell, D.E. III, R. R. Lowden, J. Hunter, C. Hannel, The Fracture Tough of Nuclear Graphite Grades, ORNL/TM-2016/678