A system for in-reactor dosimetry during materials research in SM-2 and RBT-6 reactors

Kuprienko, V. A.; Markina, N. V.; Povarova, E. V.; Ryaznov, D. K.; Boitsov, A. A.; Starostov, B.I.

doi:10.1007/bf01122054

At Energy

1988

DOI: 10.1007/bf01122054

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A system for in-reactor dosimetry during materials research in SM-2 and RBT-6 reactors

V. A. Kuprienko¹,

N. V. Markina²,

E. V. Povarova³

et al.

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“…Silicon carbide monitors were used to determine the temperature of the samples to within ±25°C in the course of irradiation [2], and the fast-neutron fluence was determined according to the induced activity of 54 Fe and 93 Nb monitors [3].…”

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confidence: 99%

Investigation of radiation creep of reactor graphite

2008

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The results of investigations of the radiation creep of GR-280 graphite under a high compression load (about 15 MPa) after irradiation in a BOR-60 reactor at 520°C to fast-neutron fluence 1.2·10 22 cm −2 are presented. It is shown that the fluence dependence of the creep deformation, calculated using the standard relation as the difference of the change in the dimensions of loaded and control samples, is anomalous. The linear thermal expansion coefficients of loaded and control samples are found as functions of the neutron fluence under the same conditions. It is noted that the linear thermal expansion coefficient of the samples irradiated under a load is much higher than that of the control samples. Simmons' theorem is used to take account of the effect of a load on the linear thermal expansion coefficient, and the dimensional changes of graphite exposed to radiation and the dependence of the true creep deformation on the neutron fluence are calculated. It is shown that these dependences are close to linear in the experimental fluence rangeCreep is an important characteristic of graphite, determining its behavior in a reactor. It gives rise to relaxation of the stresses in the graphite components of the structure, and in most cases it has a favorable effect on the negative processes occurring in the graphite elements under neutron irradiation.The creep rate is a complicated function of the irradiation conditions and the changes of the physicomechanical properties under irradiation. The study of creep under reactor irradiation is complicated by the fact that the deformation of the loaded samples is determined by the creep as well as the dimensional changes as a result of the radiation evolution of the structure, which depends strongly on the physical properties of the graphite, first and foremost, the linear thermal expansion coefficient and the elastic modulus.Irradiation Conditions and Materials. The samples were fabricated from GR-280 graphite. They consisted of 8 mm in diameter and 30 mm long cylinders cut along and across the direction of extrusion of the blocks [1]. A setup consisting of 32 control samples on eight stages (four per stage) and 12 samples under an axial compression load was developed to irradiate the loaded samples. The stress in the loaded samples was 15 MPa on average.The samples were irradiated in the core of the BOR-60 reactor at 520°C in the neutron-fluence range (0.4-1.2)·10 22 cm -2 (here and below the fluence is given for neutrons with energy >0.18 MeV). Silicon carbide monitors were used to determine the temperature of the samples to within ±25°C in the course of irradiation [2], and the fast-neutron fluence was determined according to the induced activity of 54 Fe and 93 Nb monitors [3].

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Investigation of radiation creep of reactor graphite

2008

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Comparative measurements of the neutron flux in RBT-6 reactors

Boitsov¹,

Kuprienko²,

Markina³

et al. 1990

At Energy

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A system for in-reactor dosimetry during materials research in SM-2 and RBT-6 reactors

Cited by 2 publications

References 0 publications

Investigation of radiation creep of reactor graphite

Investigation of radiation creep of reactor graphite

Comparative measurements of the neutron flux in RBT-6 reactors

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