Conclusions
Reactor RBT-6 is simple in construction and is easily accessible for conducting experiments. The values of neutron flux in it are high for small thermal power; this together with the large duration of continuous operation ensures the possibility of conducting a wide range of experimental investigationa. Such a reactor may be recommended as a research reactor for irradiation of samples of materials up to moderate flux values (1019–1021 neutrons/cm2) and for conducting experiments for studying the change in the properties of materials during irradiation, which are becoming increasingly more important. Estimates show that the number of used fuel assemblies of the SM-2 reactor are sufficient for the operation of several such reactors.
If necessary, the number of experimental channels in the active zone of such a reactor can be increased by increasing the number of fuel assemblies and the thermal power. Beryllium can be used as the lateral reflector. This results in a decrease of the volume of the active zone and the thermal power of the reactor, but increases its cost.
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Literature Cited
S. M. Feinberg et al., Third Geneva Conference, USSR Paper No. 320 (1964).
G. A. Bat', A. S. Kochenov, and L. P. Kabanov, Research Nuclear Reactors [in Russian], Atomizdat, Moscow (1972).
State System of Ensuring Uniqueness of Measurements. Determination of the Characteristics of Thermal Neutron Fields by the Activation Method, VNIIFTRI, Moscow (1972).
V. A. Tsykanov and B. V. Samsonov, Technique of Irradiation of Materials in Reactors with High Neutron Flux [in Russian], Atomizdat, Moscow (1973).
Additional information
Translated from Atomnaya Énergiya, Vol. 43, No. 1, pp. 3–7, July, 1977.
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Tsykanov, V.A., Aver'yanov, P.G., Burukin, V.P. et al. Research reactor RBT-6. At Energy 43, 599–603 (1977). https://doi.org/10.1007/BF01118499
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DOI: https://doi.org/10.1007/BF01118499