A Versatile Methodology for Reactor Pressure Vessel Aging Assessments

نویسندگان

چکیده

The operation of many nuclear pressurized water reactors is being extended beyond their design lifetime threshold. From the perspective possible further extension, satisfying safety requirements a priority. Characterization structural integrity reactor pressure vessel (RPV) an important issue as it guiding parameter that influences lifetime. Embrittlement RPV material primarily induced by bombardment fast neutrons (with energies greater than 1 MeV). Consequently, neutron fluence one quantities used authorities to characterize RPV. However, future aging assessments might lean on new variables with respect current laws, such considering whole spectrum or displacements per atom (dpa) since latter more representative overall damage generated in In order meet these challenges, versatile calculation scheme for proposed this paper. developed methodology allows compute (fast and non-fast) well dpa rate, using Norgett-Robinson-Torrens model Athermal Recombination Corrected model, wide azimuthal axial range capsules monitoring program (which contain dosimeters samples). This based coupling between deterministic (CASMO5 SIMULATE5) Monte Carlo (MCNP6) numerical approaches. First, approach evaluate full-core fission source term. Second, modeling perform attenuation from core sites interest, computational efficiency, accuracy, potential benefits are presented. Moreover, frequency at which transport calculations should be performed obtain sufficiently accurate time-integrated data over cycle discussed. Finally, validity indicator compared against use dpa.

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ژورنال

عنوان ژورنال: Nuclear Science and Engineering

سال: 2021

ISSN: ['0029-5639', '1943-748X']

DOI: https://doi.org/10.1080/00295639.2021.1991761