A platform for research: civil engineering, architecture and urbanism
A platform for research: civil engineering, architecture and urbanism
Attenuation of reactor radiations in serpentine sand
Experimental investigation of shielding properties of serpentine sand of specific weight of 1.62 g/cu cm and containing 11.5% of chemically bound water, which liberates above 450 C; absorption properties for fast and thermal neutrons and γ-rays; penetration range of fast neutron is compared with that of boron carbide, serpentinite concrete, and iron-ore concentrate. (see also English translation in Soviet Atomic Energy v 19 n 4 Oct 1965 p 1283-9)
Attenuation of reactor radiations in serpentine sand
Experimental investigation of shielding properties of serpentine sand of specific weight of 1.62 g/cu cm and containing 11.5% of chemically bound water, which liberates above 450 C; absorption properties for fast and thermal neutrons and γ-rays; penetration range of fast neutron is compared with that of boron carbide, serpentinite concrete, and iron-ore concentrate. (see also English translation in Soviet Atomic Energy v 19 n 4 Oct 1965 p 1283-9)
Attenuation of reactor radiations in serpentine sand
Oslablenie izluchenii reaktora v serpentinitovym peske
Vasil'Ev, G.A. (author) / Veselkin, A.P. (author) / Egorov, Yu.A. (author) / Moiseev, G.G. (author) / Pankrat'Ev, Yu. V. (author)
Atomnaya Energiya ; 19
1965
6 pages
Article (Journal)
Russian
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