Abstract
The authors have studied the possibility of using chromite and chomotte heat-resistant concretes for the thermal shields of reactors. They observe neutron fluxes of various intensities (up to 1013 neutrons/cm2·sec, with spectrum similar to fission spectrum), absorbed by shields of these materials. They compute the transmission of neutrons and of fluxes of gamma quanta and the heat emission in the shielding. They calculate the temperatures in the shielding for various neutron fluxes, concrete thicknesses and cooling conditions. They perform a statistical calculation of the temperature stresses for shielding constructed of heat-resistant ferroconcrete.
It was established that nuclear reactor shields can be made from heat-resistant ferroconcrete when the neutron fluxes on the concrete are up to 1013 neutrons/cm2·sec, for temperatures up to 1000–1100° C and temperature differences of up to 900° C.
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Literature Cited
A. N. Komarovskii, Construction of Nuclear Plants [in Russian], Moscow, Gosénergoizdat (1961).
J. Struct. Div.,84, 1 (1958).
D. Halliday, Heat Release in Concrete Reactor Shield HERE, R/p, 1963, Harwell (1956).
J. Lane, Nucleonics,13, No. 6, 36 (1955).
B. Price, K. Horton, and K. Spinney, Shielding against Nuclear Radiation [Russian translation], Moscow, Izd. Inostr. Lit. (1959).
Bautechnik, No. 1, 7 (1962).
K. D. Nekrasov, Heat-Resistant Concrete [in Russian], Moscow, Promstroiizdat (1957).
K. D. Nekrasov and A. V. Zotov, Preparation of Refractory Concretes and Their Applications in Thermal Plant [in Russian], Moscow, Stroiizdat (1950).
K. D. Nekrasov, Experience in the Use of Heat-Resistant Concrete in Thermal Plant [in Russian], Moscow, Gosstroiizdat (1957).
V. I. Murashov and B. A. Al'tshuler, Construction of Thermal Plant from Heat-Resistant Ferroconcrete [in Russian], Moscow, Gosstroiizdat (1958).
Instructions on the Technology of Preparation and Use of Heat-Resistant Concretes [in Russian], No. CH-156-61, Moscow, Gosstroiizdat (1962).
A. F. Milovanov, Heat-Resistant Ferroconcrete [in Russian], Moscow, Gosstroiizdat (1963).
G. Marchuk, Proceeding of Seminar, Vienna (August, 1961); Physics of Fast and Intermediate Reactors, Vol. II, Vienna (1962).
D. L. Broder, A. A. Kutuzov, V. V. Levin, and V. V. Frolov, In symposium: Topics in the Physics of Reactor Shielding [in Russian], Moscow, Gosatomizdat (1963), p. 52.
B. I. Sinitsyn and S. G. Tsypin, In symposium: Topics in the Physics of Reactor Shielding [in Russian], Moscow, Gosatomizdat (1963), p. 75.
G. I. Marchuk, Calculation Methods for Nuclear Reactors [in Russian], Moscow, Gosatomizdat (1961).
Shielding of Nuclear Reactors (Symposium), Ed. by T. Rockwell [Russian translation], Moscow, Izd. Inostr. Lit. (1963).
V. I. Murashov, Fissure Resistance, Rigidity and Strength of Ferroconcrete [in Russian], Moscow, Mashstroiizdat (1950).
Investigations on Heat-Resistant Concrete and Ferroconcrete (Symposium) [in Russian], Ed. by V. I. Murashov, Moscow, Gosstroiizdat (1954).
Instructions on Planning of Ferroconcrete Smokestacks [in Russian], Moscow, Gosstroiizdat (1962).
Provisional Directions on Planning Heat-Resistant Ferroconcrete Structures No. (U-151-56/MCPMKhP), Moscow, Gosstroiizdat (1957).
Additional information
Translated from Atomnaya Énergiya, Vol. 19, No. 6, pp. 524–529, December, 1965
Report read by G. I. Budker at the International Conference on High-Energy Accelerators (Frascati, Italy).
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Dubrovskii, V.B., Krasnoyarov, N.V., Kulakovskii, M.Y. et al. Use of concretes for high-temperature shielding of nuclear reactors. At Energy 19, 1498–1503 (1965). https://doi.org/10.1007/BF02153697
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DOI: https://doi.org/10.1007/BF02153697